• TABLE OF CONTENTS
HIDE
 Title Page
 Acknowledgement
 Table of Contents
 List of Tables
 List of Figures
 Abstract
 Introduction
 Method of calculations
 Problem description
 Results and discussions
 Conclusion
 Appendices
 References
 Biographical sketch














Title: Nuclear design analysis of square-lattice honeycomb space nuclear rocket engine
CITATION PDF VIEWER THUMBNAILS PAGE IMAGE ZOOMABLE
Full Citation
STANDARD VIEW MARC VIEW
Permanent Link: http://ufdc.ufl.edu/UF00100676/00001
 Material Information
Title: Nuclear design analysis of square-lattice honeycomb space nuclear rocket engine
Physical Description: Book
Language: English
Creator: Gouw, Reza Raymond, 1972-
Publisher: State University System of Florida
Place of Publication: Florida
Florida
Publication Date: 2000
Copyright Date: 2000
 Subjects
Subject: Nuclear rocket engines   ( lcsh )
Nuclear and Radiological Engineering thesis, M.E   ( lcsh )
Dissertations, Academic -- Nuclear and Radiological Engineering -- UF   ( lcsh )
Genre: government publication (state, provincial, terriorial, dependent)   ( marcgt )
bibliography   ( marcgt )
theses   ( marcgt )
non-fiction   ( marcgt )
 Notes
Summary: ABSTRACT: Recent studies at the Innovative Nuclear Space Power and Propulsion Institute (INSPI) at the University of Florida have demonstrated the feasibility of fabricating solid solutions of ternary carbide fuels such as (U,Zr,Nb)C, (U,Zr,Ta)C, (U,Zr,Hf)C, and (U,Zr,W)C. The square-lattice honeycomb reactor design utilizes these solid solutions of ternary carbide fuels. The reactor is fueled with a solid solution of 93% enriched (U,Zr,Nb)C. The square-lattice honeycomb design provides high strength and is amenable to the processing complexities of these ultrahigh temperature fuels. The optimum core configuration requires a balance between high specific impulse and thrust level performance, while maintaining the temperature and strength limits of the fuel. There are two types of reactor designs analyzed for this study, Intermediate-Spectrum Square-Lattice Honeycomb (IS-SLHC) and Moderated Square-Lattice Honeycomb (M-SLHC) designs. Both designs are based on a cylindrical core. Nuclear design analysis is performed using both neutron transport and diffusion theory codes. The computer code used to perform neutron transport calculation is the MCNP4B, Monte Carlo code. VENTURE is the computer code used to perform the diffusion theory calculations. Group constants for VENTURE were obtained from COMBINE by using a B-1 approximation to the neutron transport equation. For the system analysis, five axial regions are specified. In each axial region, temperature and fuel density are varied. The axial and radial power distributions for the systems are calculated, as well as the axial and radial flux distributions. The system temperature coefficients of the systems are also calculated.
Summary: ABSTRACT (cont.): A water submersion accident scenario is also analyzed for these systems. The results are compared from the four-group and the 16-group calculations. The effects of reflector thickness and core size are examined. Results, which are obtained from COMBINE/VENTURE calculations, are compared with results from MCNP calculations. Finally, the study provides a comparison between the Moderated Square-Lattice Honeycomb core, which has a relatively thermal neutron spectrum, with the Intermediate-Spectrum Square-Lattice Honeycomb design.
Thesis: Thesis (M.E.)--University of Florida, 2000.
Bibliography: Includes bibliographical references (p. 68).
System Details: System requirements: World Wide Web browser and PDF reader.
System Details: Mode of access: World Wide Web.
Statement of Responsibility: by Reza Raymond Gouw.
General Note: Title from first page of PDF file.
General Note: Document formatted into pages; contains x, 69 p.; also contains graphics.
General Note: Vita.
 Record Information
Bibliographic ID: UF00100676
Volume ID: VID00001
Source Institution: University of Florida
Holding Location: University of Florida
Rights Management: All rights reserved by the source institution and holding location.
Resource Identifier: oclc - 45825701
alephbibnum - 002566159
notis - AMT2440

Downloads

This item has the following downloads:

master ( PDF )


Table of Contents
    Title Page
        Page i
    Acknowledgement
        Page ii
    Table of Contents
        Page iii
        Page iv
    List of Tables
        Page v
    List of Figures
        Page vi
        Page vii
        Page viii
    Abstract
        Page ix
        Page x
    Introduction
        Page 1
        Page 2
        Page 3
        Page 4
        Page 5
        Page 6
        Page 7
    Method of calculations
        Page 8
        Page 9
        Page 10
        Page 11
    Problem description
        Page 12
        Page 13
        Page 14
        Page 15
        Page 16
        Page 17
        Page 18
        Page 19
        Page 20
    Results and discussions
        Page 21
        Page 22
        Page 23
        Page 24
        Page 25
        Page 26
        Page 27
        Page 28
        Page 29
        Page 30
        Page 31
        Page 32
        Page 33
        Page 34
        Page 35
        Page 36
        Page 37
        Page 38
        Page 39
        Page 40
        Page 41
        Page 42
        Page 43
        Page 44
        Page 45
        Page 46
        Page 47
        Page 48
        Page 49
        Page 50
        Page 51
        Page 52
    Conclusion
        Page 53
        Page 54
    Appendices
        Page 55
        Page 56
        Page 57
        Page 58
        Page 59
        Page 60
        Page 61
        Page 62
        Page 63
        Page 64
        Page 65
        Page 66
        Page 67
    References
        Page 68
    Biographical sketch
        Page 69
Full Text











NUCLEAR DESIGN ANALYSIS OF SQUARE-LATTICE HONEYCOMB SPACE
NUCLEAR ROCKET ENGINE














By

REZA RAYMOND GOUW


A DISSERTATION PRESENTED TO THE GRADUATE SCHOOL
OF THE UNIVERSITY OF FLORIDA IN PARTIAL FULFILLMENT
OF THE REQUIREMENTS FOR THE DEGREE OF
MASTER OF ENGINEERING

UNIVERSITY OF FLORIDA


2000















ACKNOWLEDGMENTS


This research would not be complete without the contributions of several people.

I would like to thank Dr. Samim Anghaie for his support and encouragement throughout

the entire project. His guidance and wisdom have allowed me to finish this work in a

timely fashion. I also would like to express my thanks to Dr. Edward Dugan for his

unfailing support throughout my undergraduate and graduate time at the University of

Florida. His guidance both with the research and with my curriculum was invaluable. I

would like to thank Dr. Ronald Dalton for his support and guidance during my studies at

the University of Florida. I would also like to thank Dr. John Ambrose for agreeing to

take the time and effort to be on my supervisory committee. This study would not be

complete without assistance from U.S. Department of Energy in the form of DOE

Nuclear Engineering/Health Physics Fellowship.

I would also like to express my thanks to all my colleagues and friends in the

department. Specifically, I would like to thank Richard Bowles, Robert Smith, Beth

Bruce, and Sung Kyun Jeong. Their support, suggestions, and encouragement helped me

to complete this research. Ward Dougherty, Eric Furman, and Kennita Johnson provided

invaluable support for my research throughout its entire course. Although working

tirelessly on projects of their own, they took the time and effort to review my work and

results and to offer their comments and suggestions when I asked them.















TABLE OF CONTENTS
page



A C K N O W L E D G M E N T S ...................................................................................................ii

L IST O F T A B L E S .............. ......................... .......................... ................. ....... .. ... v

LIST OF FIGURES ......................................... ............... vi

1 IN T R O D U C T IO N ..................................... ... ..................... ........... .................. 1
1.1. The Space N nuclear R ocket H history .................................................. ... .............. 1
1.2. Background Information in Honeycomb Space Nuclear Rocket Engine............. 6
2 METHOD OF CALCULATIONS ........................................................................ 8
2.1. D iffusion T heory M ethod ........................................ ......................... .............. 8
2.1.1. C O M B IN E .............................................................................. .................... 8
2.1.2. VE N TU R E ........................................................................... .................... 9
2.2. M onte C arlo M ethod.. ..................................................................... .............. 10
2.2.1. M C N P 4B .................................................. ............................................. 10
3 PR O B LEM D E SCR IPTIO N .................................................................... .............. 12
3.1. Intermediate-Spectrum Square-Lattice Honeycomb ....................................... 12
3.1.1. C ore D escrip tion ............................................................... .................... 12
3.1.2. Unit Cell Specification ...................................................... .................... 14
3.1.3. R eflector D description ................ ..................................... .................... 15
3.2. Moderated Square-Lattice Honeycomb........................................................... 16
3.2.1. C ore D escrip tion ............................................................... .................... 16
3.2.2. Unit Cell Specification ...................................................... .................... 18
3.2.3. R eflector D description ................ ..................................... .................... 20
4 RESULTS AND DISCUSSIONS ....................................................................... 21
4.1. Intermediate-Spectrum Square-Lattice Honeycomb ....................................... 25
4.1.1. F our-G roup M odel............................................................ .................... 26
4.1.2. Sixteen-Group M odel................ .................................... .................... 29
4.1.3. R eactor P aram eters........................................................... .................... 36
4.2. Moderated Square-Lattice Honeycomb ........................................................... 38
4.2.1. F our-G roup M odel............................................................ .................... 39
4.2.2. Sixteen-Group M odel................ .................................... .................... 42
4.2.3. R eactor P aram eters........................................................... .................... 49
5 CONCLUSION ..................................... .. .......... .................................... 53









APPENDICES

A SAMPLE OF COMBINE OF INPUT FILE .............. ................................... 55

B SAMPLE OF VENTURE OF INPUT FILE .......................................................... 56

C SAM PLE OF M CNP IN PU T FILE.......................................................... .............. 66

REFERENCES ........................................................ ............................ 68

B IO GRAPH ICA L SK ETCH .. ................................................................... .............. 69















LIST OF TABLES


Table page

3-1: Intermediate-Spectrum Square-Lattice Honeycomb reactor specification ........... 13

3-2: Intermediate-Spectrum Square-Lattice Honeycomb axial temperature zone
and uranium density .... .. ........................................ ......................... . . ........... ..... 15

3-3: Intermediate-Spectrum Square-Lattice Honeycomb reflector specifications.......... 16

3-4: Moderated Square-Lattice Honeycomb core specification................................ 17

3-5: Moderated Square-Lattice Honeycomb axial temperature zone and uranium
d en sity .................................................................................................... . ........... 19

3-6: Moderated Square-Lattice Honeycomb reflector specifications ............................ 20

4-1: Power fraction of Intermediate-Spectrum and Moderated Square-Lattice
Honeycomb produced from fission at sixteen different energy groups
obtained from V EN TU R E ...................................... ......................... .............. 23

4-2: Neutron mean free paths of Intermediate-Spectrum and Moderated
Square-Lattice Honeycomb obtained from VENTURE.......................................... 24

4-3: Four-group model energy structure used in both Intermediate-Spectrum and
M oderated Square-Lattice Honeycomb .............................................. .............. 24

4-4: Sixteen-group model energy structure used in both Intermediate-Spectrum and
M oderated Square-Lattice H oneycom b............................................... .............. 25

4-5: Criticality eigenvalues of four-group model, sixteen-group model, and
Monte Carlo method for Intermediate-Spectrum Square-Lattice Honeycomb ...... 26

4-6: Criticality eigenvalues of four-group model, sixteen-group model, and
Monte Carlo method for Moderated Square-Lattice Honeycomb........................ 39















LIST OF FIGURES


Figure page

3-1: Intermediate-Spectrum Square-Lattice Honeycomb core description.................. 13

3-2: Intermediate-Spectrum Square-Lattice Honeycomb fuel wafers ......................... 14

3-3: Intermediate-Spectrum Square-Lattice Honeycomb unit cell dimensions ........... 15

3-4: Moderated Square-Lattice Honeycomb fuel configuration ............................... 16

3-5: Moderated Square-Lattice Honeycomb unit cell dimension of hydrogen hole....... 19

3-6: Moderated Square-Lattice Honeycomb fuel unit cell dimension in region 2......... 19

3-7: Moderated Square-Lattice Honeycomb fuel unit cell dimension in region 3......... 20

4-1: Intermediate-Spectrum Square-Lattice Honeycomb neutron energy spectrum
obtained from C O M B IN E ................................................................... .............. 22

4-2: Moderated Square-Lattice Honeycomb neutron energy spectrum obtained
from COMBINE ..................... ......... ........ 22

4-3: Intermediate-Spectrum Square-Lattice Honeycomb four-group model
axial flux distributions obtained from VENTURE............................. .............. 27

4-4: Intermediate-Spectrum Square-Lattice Honeycomb four-group model
radial flux distributions obtained from VENTURE. ......................................... 27

4-5: Intermediate-Spectrum Square-Lattice Honeycomb four-group model
axial power distributions obtained from VENTURE. ....................................... 28

4-6: Intermediate-Spectrum Square-Lattice Honeycomb four-group model
radial power distributions obtained from VENTURE....................................... 29

4-7: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
axial flux distributions of energy groups between 16.9 MeV to
31.8 keV obtained from VEN TURE ................................................... .............. 30

4-8: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
radial flux distributions of energy groups between 16.9 MeV to
31.8 keV obtained from VEN TURE ................................................... .............. 30









4-9: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
axial flux distributions of energy groups between 31.8 keV to
0.454 keV obtained from VEN TURE ................................................. .............. 31

4-10: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
radial flux distributions of energy groups between 31.8 keV to
0.454 keV obtained from VEN TURE ................................................. .............. 31

4-11: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
axial flux distributions of energy groups between 0.454 keV to
1.86 eV obtained from VEN TURE. ....................... ........................................ 32

4-12: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
radial flux distributions of energy groups between 0.454 keV to
1.86 eV obtained from VEN TURE. ....................... ........................................ 32

4-13: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
axial flux distributions of energy groups between 1.86 eV to
0 obtained from V EN TU RE ..................................... ....................... .............. 33

4-14: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
radial flux distributions of energy groups between 1.86 eV to
0 obtained from V EN TU RE ..................................... ....................... .............. 33

4-15: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
axial power distributions obtained from VENTURE. ....................................... 35

4-16: Intermediate-Spectrum Square-Lattice Honeycomb 16-group model
radial power distributions obtained from VENTURE....................................... 35

4-17: Intermediate-Spectrum Square-Lattice Honeycomb system temperature
w o rth cu rv e ............................................................................................................. 3 6

4-18: Intermediate-Spectrum Square-Lattice Honeycomb reflector thickness
w o rth cu rv e ............................................................................................................. 3 7

4-19: Intermediate-Spectrum Square-Lattice Honeycomb core radius
worth curve. ..................................... .. 3 8

4-20: Moderated Square-Lattice Honeycomb four-group model axial flux
distributions obtained from VEN TURE ............................................. .............. 40

4-21: Moderated Square-Lattice Honeycomb four-group model radial flux
distributions obtained from VEN TURE ............................................. .............. 40

4-22: Moderated Square-Lattice Honeycomb four-group model axial power
distributions obtained from VEN TURE ............................................. .............. 41









4-23: Moderated Square-Lattice Honeycomb four-group model radial power
distributions obtained from VEN TURE ............................................. .............. 42

4-24: Moderated Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 16.9 MeV to 31.8 keV
obtained from V EN TU R E ...................................... ......................... .............. 43

4-25: Moderated Square-Lattice Honeycomb 16-group model radial flux
distributions of energy groups between 16.9 MeV to 31.8 keV
obtained from V EN TU R E ...................................... ......................... .............. 44

4-26: Moderated Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 31.8 keV to 0.454 keV
obtained from V EN TU R E ...................................... ......................... .............. 44

4-27: Moderated Square-Lattice Honeycomb 16-group model radial flux
distributions of energy groups between 31.8 keV to 0.454 keV
obtained from V EN TU R E ...................................... ......................... .............. 45

4-28: Moderated Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 0.454 keV to 1.86 eV
obtained from V EN TU R E ...................................... ......................... .............. 45

4-29: Moderated Square-Lattice Honeycomb 16-group model radial flux
distributions of energy groups between 0.454 keV to 1.86 eV
obtained from V EN TU R E ...................................... ......................... .............. 46

4-30: Moderated Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 1.86 eV to 0
obtained from V EN TU R E ...................................... ......................... .............. 46

4-31: Moderated Square-Lattice Honeycomb 16-group model radial flux
distributions of energy groups between 1.86 eV to 0
obtained from V EN TU R E ...................................... ......................... .............. 47

4-32: Moderated Square-Lattice Honeycomb 16-group model axial power
distributions obtained from VEN TURE ............................................. .............. 48

4-33: Moderated Square-Lattice Honeycomb 16-group model radial power
distributions obtained from VEN TURE ............................................. .............. 48

4-34: Moderated Square-Lattice Honeycomb system temperature worth curve. ............ 49

4-35: Moderated Square-Lattice Honeycomb reflector thickness worth curve ............. 50

4-36: Moderated Square-Lattice Honeycomb core radius worth curve......................... 51















Abstract of Thesis Presented to the Graduate School
of the University of Florida in Partial Fulfillment of the
Requirements for the Degree of Master of Engineering

NUCLEAR DESIGN ANALYSIS OF SQUARE-LATTICE HONEYCOMB SPACE
NUCLEAR ROCKET ENGINE

By

Reza Raymond Gouw

May 2000


Chairman: Samim Anghaie
Major Department: Nuclear and Radiological Engineering

Recent studies at the Innovative Nuclear Space Power and Propulsion Institute

(INSPI) at the University of Florida have demonstrated the feasibility of fabricating solid

solutions of ternary carbide fuels such as (U,Zr,Nb)C, (U,Zr,Ta)C, (U,Zr,Hf)C, and

(U,Zr,W)C. The square-lattice honeycomb reactor design utilizes these solid solutions of

ternary carbide fuels. The reactor is fueled with a solid solution of 93% enriched

(U,Zr,Nb)C. The square-lattice honeycomb design provides high strength and is

amenable to the processing complexities of these ultrahigh temperature fuels. The

optimum core configuration requires a balance between high specific impulse and thrust

level performance, while maintaining the temperature and strength limits of the fuel.

There are two types of reactor designs analyzed for this study, Intermediate-Spectrum

Square-Lattice Honeycomb (IS-SLHC) and Moderated Square-Lattice Honeycomb (M-

SLHC) designs. Both designs are based on a cylindrical core. Nuclear design analysis is









performed using both neutron transport and diffusion theory codes. The computer code

used to perform neutron transport calculation is the MCNP4B, Monte Carlo code.

VENTURE is the computer code used to perform the diffusion theory calculations.

Group constants for VENTURE were obtained from COMBINE by using a B-1

approximation to the neutron transport equation. For the system analysis, five axial

regions are specified. In each axial region, temperature and fuel density are varied. The

axial and radial power distributions for the systems are calculated, as well as the axial and

radial flux distributions. The system temperature coefficients of the systems are also

calculated. A water submersion accident scenario is also analyzed for these systems.

The results are compared from the four-group and the 16-group calculations. The effects

of reflector thickness and core size are examined. Results, which are obtained from

COMBINE/VENTURE calculations, are compared with results from MCNP calculations.

Finally, the study provides a comparison between the Moderated Square-Lattice

Honeycomb core, which has a relatively thermal neutron spectrum, with the

Intermediate-Spectrum Square-Lattice Honeycomb design.
















CHAPTER 1
INTRODUCTION


1.1. The Space Nuclear Rocket History


In 1955 nuclear propulsion research was initiated in the United States. The

technology emphasis occurred in the 1960's and was primarily associated with the

Rover/NERVA Program. Los Alamos National Laboratory (LANL) conducted the initial

tests for a series of nuclear rockets, and the program was known as the KIWI program

(Robbins, 1991). Internal structural materials for these nuclear reactors were made from

graphite for two main reasons: It has excellent properties at high temperatures, and it acts

as a moderator. As temperature of graphite increases, its strength actually increases. Its

action as a moderator reduces the amount of enriched uranium required in the core. The

biggest disadvantage of graphite is that it erodes in the presence of hot hydrogen. Many

techniques are available to reduce erosion to acceptable levels, but the erosion cannot be

eliminated (Pellacio and El-Genk, 1994).

In July 1959, the first nuclear rocket test was conducted, which was known as

KIWI A. Uncoated uranium dioxide (UO2) plates were used as fuel elements. A

maximum temperature of 2683 K and a power level of 70 MWt were reached during this

test. However, the reactor core sustained significant structural damage due to vibrations

during the operations. Nevertheless, KIWI-A successfully demonstrated the principle of

nuclear rockets. In the same month a second test, KIWI A', was conducted, and it






2


incorporated significant modifications in the core design used in KIWI A. The fuel of

this reactor was in the form of short cylindrical UO2 elements in graphite modules that

had four axial coolant channels that were coated with niobium carbide (NbC), using a

chemical vapor deposition process. A power level of 85 MWt was achieved for a 6-

minute duration. In 1960, KIWI-A' was tested again using NbC graphite module fuel

plates. UO2 was embedded in the graphite matrix. However, during its 6-minute test,

this improved design sustained some structural damage (Robbins, 1991).

The following reactor, KIWI-A3, used a thicker NbC coating, which resulted

from a higher temperature chemical vapor deposition process. However, in October 1959

during its 5-minute test, it also sustained some core damage. This test reached power

levels of 100 MWt, but it also experienced some blistering and corrosion in some fuel

elements. Generally, this reactor test was considered successful. UO2 was also used in

KIWI BlA; however, the fuel element design was changed to 66-cm in length with a 7-

channel configuration, and NbC coatings were used. In December 1961, KIWI BlA was

tested, and it was intended to reach 1100 MWt. However, due to a fire caused by a

hydrogen leak in the reactor exhaust nozzle, the test was terminated after 30 seconds, and

the power reached only 300 MWt.

In September 1962, KIWI BIB test was conducted, which was essentially a repeat

of the KIWI BlA test. A power level of 900 MWt was achieved, but the test was

terminated within a few seconds when several fuel elements were ejected from the

reactor exhaust nozzle. The KIWI B2 and KIWI B3 designs followed KIWI B IB test,

but these configurations were never tested. Considerable redesigns were incorporated in

KIWI B4A reactor based on the failure of the KIWI B B configuration. Fully-extruded









hexagonal fuel elements made from graphite blocks were used. The fuel elements were

1.32-m long and 19-mm in diameter, with 19 cooling channels. Each cooling channel

had a diameter of 2.3 mm. In November 1962, the test run was terminated due to

vibration that induced damage to the core, which produced bright flashes in the exhaust

steam. The next design configurations were KIWI B4B and KIWI B4C, but they were

never tested. With modifications in the design of the KIWI B4D reactor, the vibration

problem was eliminated; however, due to some problems in previous tests, the test that

was conducted in May 1964 was terminated due to the rupture of a nozzle cooling tube

after about 60 seconds at full power (Robbins, 1991). The KIWI B4E reactor was the

first to use coated uranium carbide (UC2) fuel, in place of the UO2 fuel. A 25-Pim layer

of pyrolytic graphite was incorporated in the uranium fuel particles to avoid oxidation of

the carbide fuel. The second benefit of this pyrolytic carbon layer was to act as a

cladding, which then subsequently enhanced fission product retention. The KIWI B4E

reactor was operated for 12 minutes, including 8 at full power. Due to the limitation of

liquid hydrogen storage capability, the test duration was limited. A series of nuclear

engine test also began in 1964. In September 1964, the NRX-A2 engine was operated for

5 minutes at half to full power levels. Due to limitation of the hydrogen storage capacity,

the duration of the test was limited. The engine demonstrated a specific impulse of 760

seconds at full power, 1100 MWt.

In January 1965, the KIWI TNT, a KIWI-B type reactor, was deliberately

destroyed by subjecting it to a fast excursion. This test was intended to confirm the

theoretical models of transient behavior. In April 1965, the NRX-A3 was operated for 8

minutes, and for 3.5 minutes of this 8-minute test, the engine operated at full power.









However, due to problem of a spurious trip from the turbine overspeed, the test was

terminated. In May 1965, the reactor test was restarted, and it operated at full power for

13 minutes. In addition, it restarted for low to medium power operations for 45 minutes.

A new class of reactors, the Phoebus lA, was first tested in June 1965. It ran for over 10

minutes of operations at 1090 MWt and reached an exhaust temperature of 2370 K. The

next NRX engine tested was the NRX-EST engine. It operated for a total of 110 minutes

that included operation at full power of 1100-1200 MWt for 28 minutes on five different

days in February 1966. Following the NRX-EST, NRX-A5 engine was operated at full

power of 1100 MWt for 30 minutes in June 1966. Again the test duration was limited

due to the limited hydrogen storage capacity.

In February 1967, based on the Phoebus 1A test, Phoebus IB was tested, and it

reached power levels of 1500 MWt for 30 minutes, with an additional 15 minutes at

lower power levels. Also in December of the same year, the NRX-A6 engine was

operated for 60 minutes at full power, 1100 MWt, and this test exceeded the NERVA

design goal. In March 1968, the first engine to operate in a downward firing position was

tested. This engine was known as XE', which was a prototype engine. It had a power

level of 1100 MWt. The next Phoebus series was Phoebus 2A with a designed power

level of 5,000 MWt, which made it the most powerful nuclear reactor of any type ever

constructed. However, in June 1968, the operations were limited to 4,000 MWt due to

premature overheating of aluminum segments of the pressure vessel clamps. This test

included intermediate power level operations and a reactor restart, and it lasted for a total

of 12.5 minutes. Zirconium carbide (ZrC) coating on some fuel elements was

incorporated in the PEWEE reactor. It successfully achieved new records for average









and peak core power density levels of 2340 MWt/m3 and 5200 MWt/m3, respectively.

These new levels were achieved while operating at 503 MWt and 2550 K. It also

demonstrated a specific impulse of 845 seconds (Robbins, 1991).

The Nuclear Furnace (NF) reactor was the final phase of NERVA fuel

development. The NF was a heterogeneous water-moderated beryllium-reflected reactor

for high-temperature nuclear testing of fuel elements and other components. Forty-seven

of the 49 fuel elements used UC2 and ZrC carbon composite fuel, while the remaining

two fuel elements used uranium-zirconium carbide. In 1972, the NF was used to test

composite fuel elements with various carbide contents to obtain thermal expansion

coefficients and thermal stress resistance. The test demonstrated that minimizing the

mismatch in thermal expansion coefficients between the fuel and coating would reduce

coating cracking and carbon erosion. The NF operated at a peak power of 44 MWt and at

2500 K. The Nuclear Furnace 2 reactor was built but not tested due to the cancellation of

all work in this area in 1972. The objectives of this experiment included testing of a

coated particle fuel using a graphite fuel matrix with a coefficient of thermal expansion

closely matched to that of the coating, to reduce thermal stress and cracking (Pelaccio

and El-Genk, 1994).

During the Rover/NERVA program, two major problems were identified. One of

the problems was core damage due to vibration that was accompanied by cracking of the

fuel matrix and loss of material into the propellant flow. The second problem was the

loss of fuel matrix uranium and carbon due to coating erosion and cracking, and through

diffusion of propellant through the coating. Core redesign that reduced vibration and

matrix cracking solved the first problem. However, the second problem, fuel element









corrosion, proved to be more difficult to solve. "Corrosion was most pronounced in the

mid-range region, about a third of the distance from the cold end of the fuel element. Fuel

operating temperatures were lower here than the fabrication temperatures, hence thermal

stresses were higher than at the hot end. Also, the neutron flux was highest in this

region...." (Horman, Napier, and Caldwell, 1991, p. 9) No fuel element geometry or fuel

material ever totally solved the NERVA fuel element degradation problem. Mass loss of

both uranium and carbon continued to limit service life by causing significant

perturbation to core neutronics during the tests. Crack development in the fuel element

coating was never completely eliminated. Non-nuclear testing of coated fuel elements

revealed an Arrhenius relationship between diffusion and temperature. For every 205 K

increase in temperature (in the range 2400 to 2700 K), the mass loss increased by a factor

of ten, resulting in loss of 20% of total uranium in approximately 5 hours of testing at

2870 K. (Horman, Napier, and Caldwell, 1991)

1.2. Background Information in Honeycomb Space Nuclear Rocket Engine


On July 20, 1989, President George Bush outlined the Space Exploration

Initiative (SEI) during the 20th anniversary of Apollo 11. President Bush called for a

return to the Moon "to stay" early in the next century, followed by a journey to Mars

using systems "space tested" in the lunar environment. The NERVA Derivative Reactor

concept is the current "baseline" concept for the Space Exploration Initiative (SEI)

missions (Borowski and Clark, 1992)

The Square-Lattice Honeycomb Space Nuclear Rocket Engine is a NERVA

Derivative Reactor core with a new nuclear fuel design. It is an attempt to reduce the

weight of the nuclear rocket engine and simplify the core design without sacrificing the






7


thrust level. There are two designs analyzed, Intermediate-Spectrum Square-Lattice

Honeycomb and Moderated Square-Lattice Honeycomb. The main difference between

these two designs is the incorporation of zirconium hydride (ZrH2) in the Moderated

Square-Lattice Honeycomb. With the utilization of ZrH2, the Moderated Square-Lattice

Honeycomb reactor is found relatively thermal in contrast to the Intermediate-Spectrum

Square-Lattice Honeycomb.
















CHAPTER 2
METHOD OF CALCULATIONS

Two methods of calculation are used to analyze the square-lattice honeycomb, the

diffusion theory method and the Monte Carlo method. For the diffusion theory method,

the computer code used is VENTURE. Group constants for VENTURE were obtained

from the COMBINE code by using a B-1 approximation to the neutron transport

equation. The MCNP4B code is used to perform the Monte Carlo analysis.

2.1. Diffusion Theory Method


2.1.1. COMBINE

COMBINE is a FORTRAN 77 computer code for the generation of spectrum-

averaged multigroup neutron cross-section data suitable for use in diffusion and transport

theory reactor design analysis. The cross-section database used by COMBINE is derived

from the Evaluated Nuclear Data Files (ENDF/B), Version 5. The energy range treated is

from 0.001 eV to 16.905 MeV spanned by a total of 166 discrete energy points/groups.

The equations solved for the energy-dependent fast and thermal neutron spectra are the

B-1 approximations to the transport equation. Two preexisting neutron spectrum codes,

PHROG (fast spectrum) and INCITE (thermal spectrum), previously developed at the

Idaho National Engineering Laboratory (INEL), were suitably integrated into a single

package to produce COMBINE (Grimesey, Nigg, and Curtis, 1990). The special

requirements necessary to operate on small computers were considered when developing

8









both the architecture and programming for a combination spectrum code. Many of the

options and approximations independently available in both of the predecessor codes

have been retained in COMBINE. The speed and enormous storage capacity of the

modern microcomputer has, in many cases, eliminated the necessity of making some of

the more limiting approximations to the transport equation for core design analysis. Input

options permit the user to select independently a fast spectrum solution, a thermal

spectrum solution, or a combined fast and thermal spectrum solution. Calculated

multigroup cross section may be issued in any of several standard formats to facilitate

interfacing with most neutron transport and diffusion codes currently in use (Grimesey,

Nigg, and Curtis 1990).

2.1.2. VENTURE

VENTURE is an IBM-PC or compatible microcomputer version of the BOLD

VENTURE system of connected codes or modules used to analyze the core of a nuclear

reactor by applying multigroup diffusion theory. The code system can analyze one, two

or three dimensions in various geometries. Variable dimensioning is used throughout the

codes, which allows for any number of energy groups and mesh points, with the

limitation that the problem fits into the core memory.

An important feature of this code system is each code module receives input from,

and writes output to, standard interface files. These unformated binary sequential files

have been specified as to format and structure by the Committee on Computer Code

Coordination (CCCC). An Input Processor reads standard interface card image format,

and converts the input to standard interface files for use by the code modules. Because

the code modules were developed over a period of years prior to the CCCC









standardization, the code modules have their own standard input format. Code dependent

or special processors read this input and rewrite it as standard interface files. The code

system is very flexible, and allows for a multitude of input options. (Shapiro, Huria, and

Cho, 1990)

2.2. Monte Carlo Method


2.2.1. MCNP4B

In general, the simulation is performed on a digital computer because the number

of trials necessary to adequately describe the phenomenon is usually quite large. The

statistical sampling process is based on the selection of random numbers-analogous to

throwing dice in a gambling casino-hence the name "Monte Carlo." MCNP4B is

written in the style of Dr. Thomas N. K. Godfrey, the principal MCNP programmer from

1975 1989. (Hendricks, 1997) It utilizes the Monte Carlo method to solve radiation

transport in matters.

The Monte Carlo method is another method for solving the transport equations.

The Monte Carlo methods are very different from deterministic transport methods. The

Monte Carlo method simulates particles interaction and keeps records of their behaviors

instead of solving an explicit equation. The average behavior of particles in the physical

system is then inferred from the average behavior of the simulated particles. The other

difference between Monte Carlo and deterministic methods is the information in the

solution. Deterministic methods gives complete information throughout the phase space

of the problem, while Monte Carlo supplies information only about specific tallies

requested by user.









Monte Carlo "solves" a transport problem by simulating particle histories rather

than by solving an equation. Nonetheless, one can derive an equation that describes the

probability density of particles in phase space; this equation turns out to be the same as

the integral transport equation. Monte Carlo works well in solving complicated three-

dimensional time-dependent problems. Since the Monte Carlo method does not use

phase space boxes, there are no averaging approximations required in space, energy, and

time. This is especially important in allowing detailed representation of all aspects of

physical data. Monte Carlo can be used to duplicate theoretically a statistical process and

is particularly useful for complex problems that cannot be modeled by computer codes

that use deterministic methods. (Hendricks, 1997)
















CHAPTER 3
PROBLEM DESCRIPTION


3.1. Intermediate-Spectrum Square-Lattice Honeycomb


The Intermediate-Spectrum Square-Lattice Honeycomb (IS-SLHC) reactor

consists of core and reflector. The core is constructed from uranium-zirconium-niobium

carbide (U,Zr,Nb)C, and the reflector is constructed from graphite.

3.1.1. Core Description

The core design is based on a set of five disk-shaped square-lattice honeycomb

fuel assemblies, which are configured into a cylindrical core. The reflected core has an

approximate critical diameter and height of 50 cm and 50 cm, respectively. Figure 3-1

shows the description of the reactor. The core is fueled with a solid solution of 93%

enriched (U,Zr,Nb)C, which is one of several ternary uranium carbides that are under

consideration for this concept. The fuel is to be fabricated as 1 mm grooved (U,Zr,Nb)C

wafers. The fuel wafers are used to form square-lattice honeycomb fuel assemblies, 10

cm in length, containing 30% cross-sectional flow area, shown in Figure 3-2 (Furman,

1999). Table 3-1 presents the reactor specifications and also shows the amount of 235U

required to make the system critical, which is determined to be 92 kg.










770 cm
550 cm
10 CM
20 cm
Reflector
Fuel I
Fuel 2
50 cm
Fuel 3
Fuel 4 100 CM
Fuel 5

Reflector


Figure 3-1 Intermediate-Spectrum Square-Lattice Honeycomb core description.





Table 3-1 Intermediate-Spectrum Square-Lattice Honeycomb reactor specification.


Properties
Diameter (cm)
Height (cm)
Radial Reflector thickness (cm)
Top Axial Reflector thickness (cm)
Bottom Axial Reflector thickness (cm)
Thickness of Fuel Assembly (cm)
Fuel Type
Fuel Enrichment (%)
Uranium Density (g/cm3)
235U amount (kg)
Propellant


Value
50
50
10
20
30
10
Solid Solution of (U,Zr,Nb)C
93
1.2 1.6
92
H2


Five fuel assemblies are stacked up axially to form the reactor core. Based on the

30% void fraction, the width of the square flow channel is about 1.3 mm. The hydrogen

propellant is passed through these flow channels and removes the heat from the reactor


core.






















Figure 3-2 Intermediate-Spectrum Square-Lattice Honeycomb fuel wafers.



3.1.2. Unit Cell Specification

Five different unit cells are used to represent the materials in the Intermediate-

Spectrum Square-Lattice Honeycomb. These unit cells correspond to the five different

temperature zones and the five axial uranium density variations in the core. Temperature

zones and axial uranium density variations are presented in Table 3-2. Figure 3-3 shows

the dimensions of the unit cell. For each unit cell, a COMBINE run was performed to

obtain the average macroscopic and microscopic cross-sections of the core. These cross-

sections were used to perform criticality calculations using VENTURE, which will also

be discussed in the later chapter. The buckling used in the unit cell is calculated based on

the geometric buckling. The unit cell is treated as homogeneous cell. The number

densities of the materials in the core are calculated. The volume fractions of the materials

are also calculated. Finally homogenized number densities of the materials are calculated

by multiplying the pure number densities with their corresponding volume fractions. The

temperature variations in the core are accommodated by the treatments of the doppler

broadening in the code. The method used to calculate the resonance region is the

Nordheim method, one of the options in COMBINE.









Table 3-2 Intermediate-Spectrum Square-Lattice Honeycomb axial temperature zone and
uranium density.

Region Axial Temperature Axial Uranium Density
(K) (g/cm3)
1 300 1.2
2 800 1.4
3 1300 1.6
4 1800 1.6
5 2300 1.4

2.3 mm--
.3 mm0.52 mm


1.26 mm




Figure 3-3 Intermediate-Spectrum Square-Lattice Honeycomb unit cell dimensions.



3.1.3. Reflector Description

For the critical system, the reflector configuration is obtained and is shown in

Table 3-3. The reflector material for this core is graphite. The bottom axial reflector

contains a 30% cross-sectional flow area, as in the fuel region. It is constructed from

graphite wafers to obtain 30% cross-sectional flow area. The average microscopic cross-

section of the reflector material is also obtained from the COMBINE run. This cross-

section is obtained by including a very small concentration of graphite in each region of

the fuel unit cell, and requesting the microscopic cross-section of graphite to be printed

out in the output file.











Table 3-3 Intermediate-Spectrum Square-Lattice Honeycomb reflector specifications.

Parameters Value
Top axial reflector thickness (cm) 20
Bottom axial reflector thickness (cm) 30
Radial reflector thickness (cm) 10
Material Graphite



3.2. Moderated Square-Lattice Honeycomb


The Moderated Square-Lattice Honeycomb (M-SLHC) is another core design that

is similar to the previous square-lattice honeycomb. However, the M-SLHC utilizes

zirconium hydride (ZrH2) to thermalize the neutron spectrum in the core. With more

themalized spectrum, the amount of 235U required is reduced significantly. The fuel

design is the same as the previous version; however in this version, the fuel assemblies

are smaller in diameter and are shaped as a cylindrical tube.

3.2.1. Core Description



Region 1 Zirconium hydride (ZrH2)
SI Fuel Elements
Region 2
Center Hole
S\ Zirconium oxide (ZrO)
Region 3 Graphite






11.0 cm



18.4 cm


Figure 3-4 Moderated Square-Lattice Honeycomb fuel configuration.









The core design is based on a set of five smaller disk-shaped square-lattice

honeycomb fuel assemblies, which are configured into cylindrical tubes. These

cylindrical tubes are then inserted into the zirconium hydride matrix. There are 18

cylindrical tubes in the core, as shown in Figure 3-4. These cylindrical tubes are

arranged into two sets of circular configurations. The smaller configuration has six

cylindrical tubes, and the larger configuration has 12. In the middle of the core, there is a

cylindrical tube made of Inconel to allow hydrogen to flow through the core. The

reflected core has a critical diameter and height of 36.8 cm and 50.0 cm, respectively.


Table 3-4 Moderated Square-Lattice Honeycomb core specification.
Properties Value
Diameter (cm) 36.8
Height (cm) 50.0
Radial Reflector thickness (cm) 10.0
Top Axial Reflector thickness (cm) 10.0
Bottom Axial Reflector thickness (cm) 0.00
Thickness of Fuel Assembly (cm) 10.0
Fuel Type Solid Solution of (U,Zr,Nb)C
Fuel Enrichment (%) 93
Uranium Density (g/cm3) 0.4 1.0
235U amount (kg) 9.2
Propellant H2


As with IS-SLHC core, the M-SLHC core is fueled with solid solution of 93%

enriched (U,Zr,Nb)C. The fuel is also to be fabricated as 1 mm grooved (U,Zr,Nb)C

wafers. The fuel wafers are then used to form square-lattice honeycomb fuel assemblies,

10 cm in length containing a 30% cross-sectional flow area; similar to IS-SLHC, only on

a smaller scale. For each cylindrical tube, five fuel assemblies are stacked up axially.

Based on the 30% void fraction, the width of the square flow channel is about 1.3 mm.

The hydrogen propellant is passed through these flow channels and removes the heat









from the reactor core. Table 3-4 shows the properties of M-SLHC. As mentioned earlier,

the amount of 235U to make the M-SLHC critical was drastically reduced compared to the

IS-SLHC. Only 9.2 kg of 235U is needed to make the M-SLHC critical, as shown in

Table 3-4.

3.2.2. Unit Cell Specification

Three regions are defined to perform the analysis as shown in Figure 3-4. Also

for this analysis, five unit cells are defined for each region in the reactor to represent the

materials in M-SLHC. These unit cells are defined as the five different temperature

zones and the five axial uranium density variations in the core. Temperature zones and

axial uranium density variations are presented in Table 3-5. Figure 3-5 describes the

dimensions of hydrogen hole unit cell in region 1. Figure 3-6 shows the dimensions of

the fuel unit cell in region 2. And finally, Figure 3-7 describes the dimension of unit fuel

cell in region 3. For each unit cell, COMBINE run is performed to obtain the average

macroscopic cross-section of the unit cell. These average macroscopic cross-sections are

then used as inputs in the VENTURE to obtain the criticality of the system. In

performing the M-SLHC analysis, two separate COMBINE runs are performed. The

buckling of the system cell is estimated using the geometric buckling. The temperature

variations in the core is accommodated by the doppler broadening treatments in the

COMBINE. The Nordheim method is used to perform the resonance calculation of the

unit cell.










Table 3-5 Moderated Square-Lattice Honeycomb axial temperature zone and uranium
density.


Axial Temperature
(K)
300
800
1300
1800
2300


Axial Uranium Density
(g/cm3)
0.4
0.6
1.0
1.0
1.0


0.25 cm


3.0 cm
2.25 cm



Hydrogen hole
- Inconel tube
ZrH2


Figure 3-5 Moderated Square-Lattice Honeycomb unit cell dimension of hydrogen hole.


0.25 cm

0.50 cmr
4.31
\ 2.50cm



S Fuel E

/ Graph


cm


element

ite


ZrO,

ZrH2


Figure 3-6 Moderated Square-Lattice Honeycomb fuel unit cell dimension in region 2.


Region









S\ 0.25 cm

/ 0.50 cm
4.26 cm
S2.50 cm



Fuel Element

SGraphite

the M-SLHC has no bottom axial reflector. The aveZrO2age cross-section of the materials in
"- ZrH2

Figure 3-7 Moderated Square-Lattice Honeycomb fuel unit cell dimension in region 3.



3.2.3. Reflector Description

For the critical system, the reflector configuration is obtained and is shown in

Table 3-6. The reflector material for this core is beryllium metal. Unlike the IS-SLHC,

the M-SLHC has no bottom axial reflector. The average cross-section of the materials in

the reflector is calculated by incorporating a very small concentration of this material in

every regions in the unit cell and requesting the microscopic cross-section to be printed in

the output.


Table 3-6 Moderated Square-Lattice Honeycomb reflector specifications.
Parameters Value
Top axial reflector thickness (cm) 10
Radial reflector thickness (cm) 10
Material Beryllium metal
















CHAPTER 4
RESULTS AND DISCUSSIONS

To better determine the characteristic of each of the designs, the neutron energy

spectrum and fraction neutron produced in fission from different neutron energies for

both designs are calculated. Figure 4-1 and Figure 4-2 present the neutron energy

spectrums for both the IS-SLHC and M-SLHC. These figures are used to determine the

neutron spectrum used to classify whether the systems are thermal or fast. Fraction

neutrons produced in fission from different neutron energies are also useful for

classifying the systems. These fractions are shown in Table 4-1. Based on the power

fractions in Table 4-1, the power of the IS-SLHC is produced by neutron in the energy

group of 8, 9, and 10. These energy groups have energy between 2.04 keV and 22.6 eV.

Based on Figure 4-1, Figure 4-2, and Table 4-1, the IS-SLHC is classified to be an

epithermal reactor because the system power is produced by neutron fission in energy in

the epithermal range. The M-SLHC can be classified as a thermal system because almost

78% of the system power is produced by neutron fission in the energy less than 0.2 eV.

Again, the size reduction of the M-SLHC can be contributed to the presence of

zirconium hydride; as well as the axial and radial beryllium reflectors. Zirconium

hydride has a high neutron scattering peak in the thermal energy range. There is a

limitation in COMBINE to account the behavior of zirconium hydride since there is only

one temperature in the COMBINE cross-section library. An analysis is performed to

determine the effect of the zirconium hydride peak by using MCNP4B. The analysis is











1.00E+00
1.00E-01
1.00E-02
1.00E-03
1.00E-04
S1.00E-05
S1.00E-06 -
1.00E-07 -
1.00E-08
1.00E-09
1.00E-10 -
1.00E-11 .




Energy (eV)


Figure 4-1 Intermediate-Spectrum Square-Lattice Honeycomb neutron energy spectrum
obtained from COMBINE.


1.00E+00
1.00E-01
1.00E-02
1.00E-03
1.00E-04
1.00E-05
1.00E-06
1.00E-07
1.00E-08
1.00E-09
1.00E-10
1.00E-11
SEnergy 0(


Energy (eV)


Figure 4-2 Moderated Square-Lattice Honeycomb neutron energy spectrum obtained
from COMBINE.









performed by varying the temperatures of zirconium hydride while keeping the other

parameters the same. The result obtained from this analysis is that the effect of

zirconium hydride is determined to be less than 1%.

To better understand the system's characteristics, the neutron mean free paths of

the system are calculated. Table 4-2 presents the neutron mean free paths of the IS-

SLHC and M-SLHC. As shown in Table 4-2, the neutron mean free path of the IS-SLHC

for energy groups of 8, 9 and 10 are 0.986 cm, 0.952 cm, and 0.933 cm. Table 4-2 also

shows the neutron mean free path of the M-SLHC for group 15 is 0.424 cm.


Table 4-1 Power fraction of Intermediate-Spectrum and Moderated Square-Lattice
Honeycomb produced from fission at sixteen different energy groups obtained from
VENTURE.
Energy Upper Limit Lower Limit Fraction of Power
Group (eV) (eV) IS-SLHC M-SLHC
1 1.69E+07 3.68E+06 0.0065 0.0017
2 3.68E+06 8.21E+05 0.0503 0.0100
3 8.21E+05 1.11E+05 0.0879 0.0094
4 1.11E+05 3.18E+04 0.0445 0.0036
5 3.18E+04 9.12E+03 0.0442 0.0039
6 9.12E+03 5.53E+03 0.0189 0.0019
7 5.53E+03 2.04E+03 0.0480 0.0054
8 2.04E+03 4.54E+02 0.1008 0.0152
9 4.54E+02 1.01E+02 0.1202 0.0273
10 1.01E+02 22.6 0.1376 0.0115
11 22.6 8.32 0.0757 0.0011
12 8.32 1.86 0.0307 0.0038
13 1.86 0.7 0.0439 0.0301
14 0.7 0.2 0.0804 0.0990
15 0.2 0.015 0.1014 0.7088
16 0.015 0 0.0091 0.0673



The results are obtained after performing deterministic and Monte Carlo analyses

on Intermediate-Spectrum and Moderated Square-Lattice Honeycomb core designs. For

deterministic analysis, four-group and sixteen-group models were used. Table 4-3 and









Table 4-4 show the energy structures for the four-group and sixteen-group models. The

flux distributions, power distributions, and criticality eigenvalues are obtained from these

analyses. Other reactor parameters are also calculated, including system temperature

coefficient, reflector thickness worth and reactor radius worth. One scenario, a water

submersion accident is analyzed.


Table 4-2 Neutron mean free paths of Intermediate-Spectrum and Moderated Square-
Lattice Honeycomb obtained from VENTURE.
Energy Upper Limit Lower Limit Mean free path (cm)
Group (eV) (eV) IS-SLHC M-SLHC
1 1.69E+07 3.68E+06 2.536 4.802
2 3.68E+06 8.21E+05 1.769 3.127
3 8.21E+05 1.11E+05 1.043 1.657
4 1.11E+05 3.18E+04 1.006 1.045
5 3.18E+04 9.12E+03 1.064 0.907
6 9.12E+03 5.53E+03 0.976 0.839
7 5.53E+03 2.04E+03 0.992 0.824
8 2.04E+03 4.54E+02 0.986 0.886
9 4.54E+02 1.01E+02 0.952 0.870
10 1.01E+02 22.6 0.933 0.901
11 22.6 8.32 0.879 0.903
12 8.32 1.86 0.964 0.901
13 1.86 0.7 0.811 0.858
14 0.7 0.2 0.680 0.770
15 0.2 0.015 0.507 0.424
16 0.015 0 0.230 0.218


Table 4-3 Four-group model energy structure used in
Moderated Square-Lattice Honeycomb.


both Intermediate-Spectrum and


Energy Upper Energy Limit Lower Energy Limit
Group (eV) (eV)
1 1.69E+07 8.21E+05
2 8.21E+05 5.53E+03
3 5.53E+03 1.86
4 1.86 0









Table 4-4 Sixteen-group model energy structure used in both Intermediate-Spectrum and
Moderated Square-Lattice Honeycomb.
Energy Upper Energy Limit Lower Energy Limit
Group (eV) (eV)
1 1.69E+07 3.68E+06
2 3.68E+06 8.21E+05
3 8.21E+05 1.11E+05
4 1.11E+05 3.18E+04
5 3.18E+04 9.12E+03
6 9.12E+03 5.53E+03
7 5.53E+03 2.04E+03
8 2.04E+03 4.54E+02
9 4.54E+02 1.01E+02
10 1.01E+02 22.6
11 22.6 8.32
12 8.32 1.86
13 1.86 0.7
14 0.7 0.2
15 0.2 0.015
16 0.015 0



4.1. Intermediate-Spectrum Square-Lattice Honeycomb


The results that will be presented in this section are flux distributions, power

distributions, criticality eigenvalue, fuel temperature worth, reflector thickness worth, and

core radius worth of Intermediate-Spectrum Square-Lattice Honeycomb. These

parameters are presented for deterministic and stochastic analyses. The deterministic

results are obtained from four-group and sixteen-group models. Table 4-5 presents the

criticality eigenvalues obtained from the four-group model, sixteen-group model, and the

Monte Carlo method. The Monte Carlo method was used to benchmark the results

obtained from the deterministic method. As shown in Table 4-5, the eigenvalues are

different from each method, as expected. The differences in these values are due to the

different methods, different cross-section library, and different discrete energy groups.













Table 4-5 Criticality eigenvalues of four-group model, sixteen-group model, and Monte
Carlo method for Intermediate-Spectrum Square-Lattice Honeycomb.
Method Eigenvalue Error
4-group model 0.9803 0.000001
16-group model 1.0046 + 0.000001
Monte Carlo 0.9460 + 0.00016


4.1.1. Four-Group Model

For preliminary calculations, the four-group model is utilized. The energy

structures are described in previous section in Table 4-3. This model is used for a quick

analysis to approximate the critical size of the reactor.

4.1.1.1. Axial and radial flux distribution

Figure 4-3 and Figure 4-4 describe the IS-SLHC four-group model axial and

radial flux distributions. From Figure 4-3, the axial peaks of neutron flux can be found

between fuel region one and two because the fuel temperature is lower at this region.

Lower temperature contributes to the lower Doppler broadening effect compare to the

higher temperature regions. The high uranium enrichment in fuel region three and four

produce high neutron absorption which reducing the neutron flux. The axial neutron flux

peak at the top graphite reflector region shows that the neutron are being slowed down

and reflected back into the core. The bottom axial reflector is composed of graphite

containing hydrogen holes to allow the heated hydrogen gas to pass through the nozzles.

Figure 4-4 shows neutron peaking in the graphite reflector region for energy groups three

and four, which represent low energy neutrons.












7.00E-04
S-*-1.69E+07 eV- 8.21E+05 eV
-=-8.21E+05 eV 5.53E+03 eV
6.00E-04 -5.53E+03 eV 1.86 eV
1.86 eV 0

5.OOE-04- o

4.00E-04 -_ _


/ 3.00E-04 _


2.00E-04


1.00E-04

0.00E+00 ---- - \--
0 10 20 30 40 50 60 70 80 90 100
Axial Location (cm)


Figure 4-3 Intermediate-Spectrum Square-Lattice Honeycomb four-group model axial
flux distributions obtained from VENTURE.


4.00E-04


3.50E-04


3.OOE-04


2.50E-04


. 2.00E-04

1.50E-04


1.OOE-04


5.00E-05

0.OOE+00


0 5 10 15 20
Radius (cm)


25 30 35


Figure 4-4 Intermediate-Spectrum Square-Lattice Honeycomb four-group model radial
flux distributions obtained from VENTURE.










4.1.1.2. Axial and radial power distribution


Figure 4-5 and Figure 4-6 show the axial and radial power distributions for IS-

SLHC. From Figure 4-5, axial power peaking is 2.51 and is encountered at the first fuel

region. The high peaking power at the top of the core can be contributed to the top axial

graphite reflector because a lower energy neutron are being reflected back into the core

by the top graphite reflector. The lower energy neutrons have a large fission cross-

section which contribute to a higher power. Also higher uranium enrichment in the next

regions caused more neutron absorption reducing the core power. Based on Figure 4-4,

the radial power peaking is found in the center of the core. The value of radial power

peaking is 1.41.




3.00----------------------------------------
3.00


2.50 -


2.00




1.00


0.50


0.00 .
0 5 10 15 20 25 30 35 40 45 50
Axial Location (cm)

Figure 4-5 Intermediate-Spectrum Square-Lattice Honeycomb four-group model axial
power distributions obtained from VENTURE.










1.60

1.40

1.20

Mo 1.00

S0.80

0.60

0.40

0.20

0.00
0 5 10 15 20 25
Radius (cm)

Figure 4-6 Intermediate-Spectrum Square-Lattice Honeycomb four-group model radial
power distributions obtained from VENTURE.



4.1.2. Sixteen-Group Model


After an approximate critical dimension is determined, sixteen-group model is

used to perform more precise calculations. The sixteen-group model energy structures

are described in Table 4-4.

4.1.2.1. Axial and radial flux distribution


Figure 4-7 and Figure 4-8 present the IS-SLHC 16-group model axial and radial

flux distributions for neutron energy between 16.9 MeV and 31.8 keV. The IS-SLHC 16-

group-model axial and radial flux distributions for neutron energy between 31.8 keV and

0.454 keV are presented in Figure 4-9 and Figure 4-10. Figure 4-11 and Figure 4-12

show the IS-SLHC 16-group model axial and radial flux distributions for neutron energy

between 0.454 keV and 1.86 eV. Figure 4-13 and Figure 4-14 show the IS-SLHC 16-

group model axial and radial flux distributions for neutron energy between 1.86 eV and 0.












S-- 1.69E+07 eV 3.68E+06 eV
S -- 3.68E+06 eV- 8.21E+05 eV
3.00E-04- -8.21E+05 eV- 1.11E+05 eV
3.E-04 1.11E+05 eV 3.18E+04 eV

2.50E-04 -- 8


2.00E-04 -


1.50E-04-


1.OOE-04 -- --


5.00E -05 -- -- __ | ------


O.OOE+00 .' . '...
0 10 20 30 40 50 60 70 80 90 100
Axial Location (cm)


Figure 4-7 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 16.9 MeV to 31.8 keV obtained from VENTURE.


1.80E-04

1.60E-04

1.40E-04

1.20E-04

1.OOE-04

I8.00E-05

6.00E-05

4.00E-05

2.00E-05

0.OOE+00


0 5 10 15 20
Radius (cm)


25 30 35


Figure 4-8 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model radial
flux distributions of energy groups between 16.9 MeV to 31.8 keV obtained from
VENTURE.


-*- 1.69E+07 eV 3.68E+06 eV
---3.68E+06 eV- 8.21E+05 eV
--8.21E+05 eV- 1.11E+05 eV
1.11E+05 eV 3.18E+04 eV



Fuel Region


S Reflector
Region












9.00E-05
9 -*-3.18E+04 eV- 9.12E+03 eV
=_- _9.12E+03 eV 5.53E+03 eV
8.OOE-05
8.00E-05 5.53E+03 eV 2.04E+03 eV
i i 2.04E+03 eV- 4.54E+02 eV
7.00E-05 -

6.00E-05 -o--- -

5.00E-05 _______|

4.00E-05 /o'

3.00E-05

2.0 oE -o //

L.OOE-05--

0.OOE+00 -
0 10 20 30 40 50 60 70 80 90 100
Axial Location (cm)


Figure 4-9 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 31.8 keV to 0.454 keV obtained from
VENTURE.


5.00E-05

4.50E-05

4.00E-05

3.50E-05

3.00E-05

2.50E-05

2.00E-05

1.50E-05

1.OOE-05

5.00E-06

0.OOE+00


0 5 10 15 20 25 30 35
Radius (cm)


Figure 4-10 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model radial
flux distributions of energy groups between 31.8 keV to 0.454 keV obtained from
VENTURE.


3.18E+04 eV 9.12E+03 eV
9.12E+03 eV 5.53E+03 eV
5.53E+03 eV 2.04E+03 eV
2.04E+03 eV 4.54E+02 eV



Fuel Region


Reflector
Region












5.00E-05 ,
S\i --4.54E+02 eV- 1.01E+02 eV
4.50E-05 1 1.01E+02 eV- 22.6 eV
S -- 22.6eV- 8.32eV
4.E-05 -8.32 eV- 1.86 eV
4.00E-05 -

3.50E-05 -\ I

3.00E-05 -----

2.50E-05 -!

2.OOE-05 ~ -

1.50E-05

1.OOE-05 ---

5.OOE-06 -< L -- ___ ______-

O.OOE 00
0 10 20 30 40 50 60 70 80 90 100
Axial Location (cm)


Figure 4-11 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model axial
flux distributions of energy groups between 0.454 keV to 1.86 eV obtained from
VENTURE.





1.20E-05
-*-4.54E+02 eV- 1.01E+02 eV
1.01E+02 eV 22.6 eV
100E-05 22.6 eV 8.32 eV
8.32 eV 1.86 eV


8.00E-06
Fuel Region

6.00E-06 Reflector
z Region

4.00E-06


2.00E-06


0.OOE+00
0 5 10 15 20 25 30 35
Radius (cm)


Figure 4-12 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model radial
flux distributions of energy groups between 0.454 keV to 1.86 eV obtained from
VENTURE.











4.50E-05


4.00E-05 -- 0.2 eV 0.015 eV
0.015 eV 0
3.50E-05 -

3.00E-05
S2.50E -05 / -- ^ l --- ---------

| 2.00E-05


1.50E-05 --

1.00E-05 ____



0.OOE+00 II
0 10 20 30 40 50 60 70 80 90 100
Axial Location (cm)


Figure 4-13 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model axial
flux distributions of energy groups between 1.86 eV to 0 obtained from VENTURE.





1.40E-06
-- 1.86 eV 0.7 eV
-- 0.7 eV 0.2 eV
1.20E-06 -0.2 eV 0.015 eV
0.015 eV 0

1.OOE-06


8.00E-07
Fuel Region

S6.00E-07
6O0 --^ 1 Reflector

4.00E-07 Region


2.00E-07 = _


O.OOE+00 -- ,
0 5 10 15 20 25 30 35
Radius (cm)


Figure 4-14 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model radial
flux distributions of energy groups between 1.86 eV to 0 obtained from VENTURE.









Based on these figures, the peaks of neutron flux can be observed between the

fuel region one and two as shown in the four-group model. The effect of graphite

reflector can be observed in Figure 4-9 and Figure 4-10. Figure 4-9 shows an increase of

neutron flux in the top and bottom graphite reflector regions for the three lower energy

groups. An increase of neutron flux can also be observed in the reflector region in Figure

4-10. A more dramatic effect of the graphite reflector can be observed in Figure 4-11,

Figure 4-12, Figure 4-13, and Figure 4-14.

4.1.2.2. Axial and radial power distribution

As presented in Four-Group Model, Figure 4-15 and Figure 4-16 show the axial

and radial power distributions for IS-SLHC. However, the value of axial power peaking

in Figure 4-15 is 2.49, slightly lower than from Figure 4-5. The difference in values is

due to the different number of energy groups. As shown Figure 4-5, the maximum axial

power peaking in Figure 4-15 is encountered at the first fuel region. The high peaking

power at the top of the core can be contributed to the top axial graphite reflector because

a lower energy neutron are being reflected back into the core by the top graphite reflector.

The lower energy neutrons have a large fission cross-section which contribute to a higher

power. Also higher uranium enrichment in the next regions caused more neutron

absorption reducing the core power. Based on Figure 4-16, the radial power peaking is

found in the center of the core. The value of radial power peaking is 1.40.












2.50



2.00 ,




1.00 -------







0.50



0.00 ,
0 5 10 15 20 25 30 35 40 45 50
Axial Location (cm)


Figure 4-15 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model axial
power distributions obtained from VENTURE.


1.60

1.40

1.20

1.00

S0.80

0.60

0.40

0.20

0.00


0 5 10 15 20
Radius (cm)


Figure 4-16 Intermediate-Spectrum Square-Lattice Honeycomb 16-group model radial
power distributions obtained from VENTURE.










4.1.3. Reactor Parameters


Other than the flux and power distributions, several reactor parameters are also

analyzed. The temperature effect in the fuel is analyzed to determine the system

temperature coefficient. The effects of reflector thickness and core size are analyzed.

The results are then plotted to show the variations of these parameters in the core.

4.1.3.1. System Temperature vs. keff


Figure 4-17 describes the system temperature coefficients. As shown in Figure 4-

17, the system temperature coefficients are negative; however, they become less negative

as the temperature increases. These negative coefficients are a very good safety feature

for this reactor. In case of an accident, the reactor power will stabilize itself because as

temperature increases, reactor power decreases.


1.23 -
keff 3E-20T6 3E-16T5 + 1E-12T4 2E-09T3 + 2E-06T2 0.0013T + 1.4531
1.21

1.19

1.17

S1.15

1.13

1.11

1.09

1.07 -
0 500 1000 1500 2000 2500
Temperature (K)

Figure 4-17 Intermediate-Spectrum Square-Lattice Honeycomb system temperature
worth curve.










4.1.3.2. Reflector size vs. keff


Figure 4-18 presents the effect of reflector thickness in the reactor. As predicted,

the reflector thickness coefficients are positive and become less positive as the reflector

thickness increases. From Figure 4-18, the reflector thickness required to make the

reactor critical is around 9 cm. The reflector thickness selected for this reactor is 10 cm,

due to the required power for power maneuvering.


1.05
keff= -0.000182 + 0.0078 + 0.9468
1.04

1.03

1.02

1.01



0.99

0.98

0.97 -
0 5 10 15 20 25
Reflector Thickness (cm)

Figure 4-18 Intermediate-Spectrum Square-Lattice Honeycomb reflector thickness worth
curve.



4.1.3.3. Core size vs. keff


Figure 4-19 shows the reactor core radius coefficients are positive as predicted;

however, the coefficients become less positive as the size increases, and they finally

become constant. Also Figure 4-19 shows that the critical radius of the core is about 25

cm, which is the radius for this reactor.










1.20
keff = -7E-07R4 + 9E-05R3 0.0047R2 + 0.1122R 0.0647
1.10


1.00


0.90


0.80


0.70


0.60 .
0 5 10 15 20 25 30 35 40 45
Core Radius (cm)

Figure 4-19 Intermediate-Spectrum Square-Lattice Honeycomb core radius worth curve.



4.1.3.4. Water submersion accident analysis


Water submersion accident scenario is analyzed for the IS-SLHC core. For this

analysis, the hydrogen holes are filled with water, and the reactor is surrounded by water.

The analysis is performed at room temperature because water has the highest density at

this temperature. The eigenvalue for this water submersion accident for the IS-SLHC is

0.8716. Therefore, the IS-SLHC will be subcritical in case of the water submersion

accident, which is a very desirable feature for the reactor.


4.2. Moderated Square-Lattice Honeycomb


The results that will be presented in this section are obtained for Moderated

Square-Lattice Honeycomb, and they are flux distributions, power distributions,

criticality eigenvalue, fuel temperature worth, reflector thickness worth, and core radius

worth. These parameters are presented for deterministic and stochastic analyses. The









deterministic results are obtained from four-group and sixteen-group models. Table 4-6

presents the criticality eigenvalues obtained from the four-group model, sixteen-group

model, and the Monte Carlo method. The Monte Carlo method is used to benchmark the

results obtained from the deterministic method.


Table 4-6 Criticality eigenvalues of four-group model, sixteen-group model, and Monte
Carlo method for Moderated Square-Lattice Honeycomb.
Method Eigenvalue Error
4-group model 0.8460 + 0.000001
16-group model 1.0163 0.000001
Monte Carlo 1.1263 + 0.00028


4.2.1. Four-Group Model

As in IS-SLHC, the four-group model is used to determine an approximation of

critical dimension of the M-SLHC. The energy structures are the same as the energy

structures used in the IS-SLHC.

4.2.1.1. Axial and radial flux distribution

Figure 4-20 and Figure 4-21 describe the M-SLHC four-group model axial and

radial flux distributions. From Figure 4-20, the peaks of neutron flux for neutron energy

group four in the fuel region one can be contributed to the top Be-reflector. The Be n-2n

reaction produces neutron which are reflected back into the top part of the core. Figure

4-21 shows a slight neutron peaking in the beryllium reflector region for energy group

three that represents low energy neutrons.












8.00E-04 ---- i --------------------
8.00E04 -*- 1.69E+07 eV 8.21E+05 eV
S8.21E+05 eV 5.53E+03 eV
7.00E-04 --- 5.53E+03 eV 1.86 eV
S& 1.86 eV 0
6.00E-04

5.00E-04 -
Be Reflector
4.00E-04 -- -

3.00E-04 -----

2.00E-04 --<

1.00E-04 ---.

O.OE000 00
0 10 20 30 40 50 60
Axial Location (cm)


Figure 4-20 Moderated Square-Lattice Honeycomb four-group model axial flux
distributions obtained from VENTURE.





7.00E-04
*- 1.69E+07 eV 8.21E+05 eV
8.21E+05 eV 5.53E+03 eV
6.00E-04 5.53E+03 eV 1.86 eV
.00E-04 1.86 eV 0

5.00E-04 --- ^ ^ ^ -- ^ -----------


4.00E-04
Fuel Region 1 Be Reflector

3.00E-04 Fuel Region 2


2.00E-04


1.00E-04 -


0.00E+00
0 5 10 15 20 25 30
Radius (cm)


Figure 4-21 Moderated Square-Lattice Honeycomb four-group model radial flux
distributions obtained from VENTURE.










4.2.1.2. Axial and radial power distribution


Figure 4-22 and Figure 4-23 show the axial and radial power distributions for the

M-SLHC. From Figure 4-22, axial power peaking is 2.75, and it is encountered at the

first fuel region. The high peaking power at the top of the core can be contributed to the

top axial beryllium reflector which reflected thermal neutron back into the core. Also

higher enrichment in the following region contributes to more neutron absorption and

reducing the neutron flux as shown in Figure 4-20. Based on Figure 4-23, the radial

power peaking curve of the M-SLHC has a power peaking in the first fuel region due to

some moderation from hydrogen in the center hole. The value of radial power peaking is

1.40.


3.00 -


2.50 _____/-- --- __ _ _ ---- ----__-----------------------
2.50 .


2.00 -


1.50 1


1.00 -


0.50 *


0.00
0 5 10 15 20 25 30 35 40 45 50
Axial Location (cm)

Figure 4-22 Moderated Square-Lattice Honeycomb four-group model axial power
distributions obtained from VENTURE.










1.60

1.40 -

1.20 -

1.00

0.80 --

0.60 .21

0.40

0.20

0.00 ---..-
0 2 4 6 8 10 12 14 16 18 20
Radius (cm)

Figure 4-23 Moderated Square-Lattice Honeycomb four-group model radial power
distributions obtained from VENTURE.



4.2.2. Sixteen-Group Model


After an approximate critical dimension is determined, the sixteen-group model is

used to perform more precise calculation, a similar method as the IS-SLHC. The sixteen-

group model energy structures are also described in Table 4-4.

4.2.2.1. Axial and radial flux distribution


Figure 4-24 and Figure 4-25 present the M-SLHC's 16-group model axial and

radial flux distributions for neutron energy between 16.9 MeV and 31.8 keV. The M-

SLHC's 16-group-model axial and radial flux distributions for neutron energy between

31.8 keV and 0.454 keV are presented in Figure 4-26 and Figure 4-27. Next, Figure 4-28

and Figure 4-29 show the M-SLHC's 16-group model axial and radial flux distributions

for neutron energy between 0.454 keV and 1.86 eV. Finally, Figure 4-30 and Figure 4-31










show the M-SLHC's 16-group model axial and radial flux distributions for neutron

energy between 1.86 eV and 0.


2.OOE-04 _
2.00E-04 1.69E+07 eV 3.68E+06 eV
1.80E-04 -'3.68E+06 eV- 8.21E+05 eV
8.21E+05 eV- 1.11E+05 eV
1.60E-04 1.11E+05 eV 3.18E+04 eV ______7

1.40E-04 - a-

S 1.20E-04 ---- ----

S-1.00E-04 -


6.00E-05 ---

4.00E-05

2.00E-05

0.OOE 00
0 10 20 30 40 50 60
Axial Location (cm)


Figure 4-24 Moderated Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 16.9 MeV to 31.8 keV obtained from VENTURE.




The thermal neutron spectrum of the M-SLHC is contributed to the moderation by

zirconium hydride in the core. In Figure 4-24 and Figure 4-25, the effect of the beryllium

reflector can be observed by the flux peaking in these regions. From Figure 4-24 and

Figure 4-25, the moderation effect of zirconium hydride can also be observed by the high

neutron concentration in energies between 3.68 MeV and 111 keV. In Figure 4-26 and

Figure 4-27, the effect of the beryllium reflector can further be seen. Figure 4-26 shows

an obvious neutron flux peaking in the top beryllium reflector region. A neutron flux

peaking can also be observed in the reflector region in Figure 4-27. Figure 4-27 also

shows flux drop in the center of the core due to the center hydrogen hole. The flux drop

in the center of the core can also be observed in previous figure, Figure 4-25. However,













2.50E-04




2.00E-04


1.50E-04 -




9 1.00E-04


Cl
C
I)


10 15
Radius (cm)


- 1.69E+07 eV 3.68E+06 eV
- -3.68E+06 eV- 8.21E+05 eV
- -8.21E+05 eV- 1.11E+05 eV
1.11E+05 eV 3.18E+04 eV


C
0
0
0


20 25 30


Figure 4-25 Moderated Square-Lattice Honeycomb 16-group model radial flux
distributions of energy groups between 16.9 MeV to 31.8 keV obtained from VENTURE.


5.00E-05




4.00E-05




3.00E-05




9 2.00E-05




1.OOE-05




0.OOE+00


0 10 20 30
Axial Location (cm)


40 50 60


Figure 4-26 Moderated Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 31.8 keV to 0.454 keV obtained from
VENTURE.


C ^
___


5.00E-05


0.00E+00


-%












5.00E-05
-*-3.18E+04 eV- 9.12E+03 eV
4.50E-05 -- -9.12E+03 eV- 5.53E+03 eV
S' 5.53E+03 eV 2.04E+03 eV

4.00E-05 ..-*-- 2.04E+03 eV 4.54E+02 eV

3.50E-05

3.00E-05

2.50E-05 ---- ,

2.00E-05 ------, -- 0

1.50E-05 -

1.00E-05 -- .----------

5.00E-06 -

0.00E+00 ,
0 5 10 15 20 25 30
Radius (cm)


Figure 4-27 Moderated Square-Lattice Honeycomb 16-group model radial flux
distributions of energy groups between 31.8 keV to 0.454 keV obtained from
VENTURE.


5.00E-05



4.00E-05



3.00E-05



g 2.00E-05



1.OOE-05



0.OOE+00


10 20 30
Axial Location (cm)


40 50 60


Figure 4-28 Moderated Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 0.454 keV to 1.86 eV obtained from VENTURE.












4.50E-05 -*-4.54E+02 eV- 1.01E+02 eV
- 1.01E+02 eV 22.6 eV
4.00E-05 -- 22.6 eV 8.32 eV
8.32 eV -1.86 eV
3.50E-05

3.00E-05 -- -

2.50E -05 - --- ---

S2.00E-05

1.50E-05 ---.,_ \

1.00E-05 -

5.00E-06 -

0.OOE+ 00
0 5 10 15 20 25 30
Radius (cm)


Figure 4-29 Moderated Square-Lattice Honeycomb 16-group model radial flux
distributions of energy groups between 0.454 keV to 1.86 eV obtained from VENTURE.


4.00E-04 _

3.50E-04


3.00E-04

2.50E-04


2.00E-04 -- -
1.50E-04 -- --- -

.00E-04



5.00E-05 -


0.OOE+00
0 10 20 30
Axial Location (cm)


40 50 60


Figure 4-30 Moderated Square-Lattice Honeycomb 16-group model axial flux
distributions of energy groups between 1.86 eV to 0 obtained from VENTURE.










3.00E-04
-- 1.86 eV 0.7 eV
---0.7 eV 0.2 eV
0.2 eV- 0.015 eV
2.50E-04 0.015 eV 0


2.00E-04 -


1.50E-04 -


.00E-04 -


5.00E-05


O.OOE+00 ....--
0 5 10 15 20 25 30
Radius (cm)

Figure 4-31 Moderated Square-Lattice Honeycomb 16-group model radial flux
distributions of energy groups between 1.86 eV to 0 obtained from VENTURE.



in Figure 4-29 and Figure 4-31, the trend is reversed because these figures show the low

energy neutrons. The hydrogen gas in the center hole acts as moderator and slows down

the neutron from fission and higher energies.

4.2.2.2. Axial and radial power distribution


As presented in the Four-Group Model, Figure 4-32 and Figure 4-33 show the

axial and radial power distributions for the M-SLHC. However, the value of axial power

peaking in Figure 4-32 is 2.10, lower than from Figure 4-22. The difference in values is

due to the different number of energy groups. As in Figure 4-22, the maximum axial

power peaking in Figure 4-32 is encountered at the first fuel region. The high peaking

power at the top of the core can be contributed to the top axial beryllium reflector which

reflected thermal neutron back into the core. Also higher enrichment in the following

region contributes to more neutron absorption and reducing the neutron flux as shown in













2.50







1.50 ----,



1.00 _----




0.50



0.00
0 5 10 15 20 25 30 35 40 45 50
Axial Location (cm)


Figure 4-32 Moderated Square-Lattice Honeycomb 16-group model axial power
distributions obtained from VENTURE.


0.80


0.60


4 6 8 10
Radius (cm)


12 14 16 18 20


Figure 4-33 Moderated Square-Lattice Honeycomb 16-group model radial power
distributions obtained from VENTURE.


Cl
------ 0 -------


oJ~
0


0










Figure 4-31. In Figure 4-33, the radial power peaking curve of the M-SLHC has the

same shape as in Figure 4-23. The power peaking is found in the first fuel region of the

core. The value of radial power peaking is 1.35. As for the axial power peaking, the

radial power peaking value is different from the value in Figure 4-23 due to the different

number of groups.

4.2.3. Reactor Parameters


As for the Intermediate-Spectrum Square-Lattice Honeycomb reactor, several

reactor parameters are also analyzed. The temperature effect in the core is analyzed to

determine the system temperature coefficient. The effects of reflector thickness and core

size are analyzed. The results are then plotted to show the variations of these parameters

in the core.


1.340
Kef= 3E-21T6 4E-17T5 + 2E-13T4 3E-10T3 + 4E-07T 0.0003T + 1.383
1.335


1.330


1.325


1.320


1.315 -


1.310 -..
0 500 1000 1500 2000 2500 3000
Temperature (K)

Figure 4-34 Moderated Square-Lattice Honeycomb system temperature worth curve.










4.2.3.1. System Temperature vs. keff


Figure 4-34 describes the system temperature coefficients of the reactor. As

shown in Figure 4-34, the system temperature coefficients are negative; however, they

become less negative as the temperature increases. As in the IS-SLHC, the negative

coefficients are very good safety feature for the M-SLHC. Therefore, in case of an

accident, the reactor power will stabilize itself because as temperature increases, reactor

power decreases.

4.2.3.2. Reflector size vs. keff


Figure 4-35 presents the effect of reflector thickness in the reactor. As predicted,

the reflector thickness coefficients are positive and become less positive as the reflector

thickness increases. From Figure 4-35, the reflector thickness required to make the

reactor critical is around 6 cm. The reflector thickness selected for this reactor is 10 cm,

because of the required power for power maneuvering.


1.12

1.1

1.08 -

1.06

1.04-62
Kf f -0.00062 0.023 +0.8616
1.02



0.98

0.96 *

0.94 -
0 5 10 15 20 25
Reflector Thickness (cm)

Figure 4-35 Moderated Square-Lattice Honeycomb reflector thickness worth curve.










4.2.3.3. Core size vs. keff


Figure 4-36 shows the reactor core radius coefficients are positive as predicted;

however, the coefficients become less positive as the size increases. Figure 4-36 shows

that the radius requirement to make the reactor critical is about 16 cm. The actual reactor

radius is 18.4.


1.25

1.2

1.15

1.1
,= -0.0007R2 + 0.0504R+ 0.3595
1.05




0.95

0.9 -
10 15 20 25 30 35
Core Radius (cm)

Figure 4-36 Moderated Square-Lattice Honeycomb core radius worth curve.



4.2.3.4. Water submersion accident analysis


A Water submersion accident scenario is also analyzed for the M-SLHC core.

For this analysis, the hydrogen holes are also filled with water, and the reactor is

surrounded by water. The analysis is performed at room temperature because water has

the highest density at this temperature. The eigenvalue for this water submersion

accident for the M-SLHC is 1.3513. Therefore, the M-SLHC will be supercritical in case






52


of the water submersion accident. This performance is not desirable in the reactor

system.
















CHAPTER 5
CONCLUSION

After observing the results discussed in Chapter 4, both the Square-Lattice

Honeycomb designs have several advantages and disadvantages. The IS-SLHC has a

desirable performance in the water submersion accident by maintaining the subcriticality,

while M-SLHC becomes supercritical if it is submerged under water. However, the M-

SLHC significantly reduces the amount of 235U needed to make the system critical. The

amount of 235U in the M-SLHC is 9.2 kg compared to 92 g for the IS-SLHC. The

reduction of 235U is largely contributed to the M-SLHC's softer spectrum. The addition

of zirconium hydride in the M-SLHC provides neutron moderation for the system;

therefore, a softer neutron spectrum. The utilization of the beryllium reflector provides

additional neutrons from its n-2n reactions, which contributes to the 235U reduction for

the M-SLHC. The M-SLHC is more compact compared to the IS-SLHC. The M-SLHC

has a core radius and height of 18.4 cm and 50.0 cm; compared to the IS-SLHC core

radius and height, 25.0 cm and 50.0 cm, respectively. Again, the size reduction of the M-

SLHC can be contributed to the presence of zirconium hydride; as well as the axial and

radial beryllium reflectors. Zirconium hydride has a high neutron scattering peak in the

thermal energy range. There is a limitation in COMBINE to account the behavior of

zirconium hydride since there is only one temperature in the COMBINE cross-section

library. An analysis is performed to determine the effect of the zirconium hydride peak

by using MCNP4B. The analysis is performed by varying the temperatures of zirconium









hydride while keeping the other parameters the same. The result obtained from this

analysis is that the effect of zirconium hydride peak is determined to be insignificant.

Both the IS-SLHC and the M-SLHC have negative fuel temperature coefficients.

This feature is very desirable for the system because as the temperature of the fuel

increases, the power level decreases. The temperature coefficients of both systems

become less negative as the temperature increases; an expected result for a highly

enriched uranium system.

Further analysis is required for both of these systems. The thermal hydraulic

analysis has to be performed to determine the thermal hydraulic performance of the

systems and to obtain more accurate temperature profiles across the systems. Neutronics

analysis needs to be performed again using the new temperature profile across the

system. Zirconium hydride is a very interesting substance and further analysis is

required. The neutron scattering spectrum of zirconium hydride needs to be analyzed,

and the mechanical performance of zirconium hydride under extremely high temperature

also needs to be considered.






















APPENDIX A

SAMPLE OF COMBINE OF INPUT FILE


=Honeycomb Core For 1.2 Density
1010101 1 1 1 1 6 16
1010102 1 0 0 0 0 0
1010201 166 158 152 144 139 134
1020101 0 0 3 3 3 0
1030101 12 1 101 0 1 2


1030203
1041001
1041002
1041003
1042001
1042002
1042003
1042004
1042005
1042006
1043011
1043012
1043013
1043021
1043022
1043023
1043061
1043062
1043063
2010401
2010511
2010521
2010522
2010523
2010531
2010532
2010533


1 612 0 0 0
4.49-02 4.49-02
0.1924700 0.19247000
300.0 300.0
501.0 92.23805
502.0 92.23505
506.0 6.00302
509.0 1.10293
583.0 40.00005
607.0 41.09304
300.0 1.0
2.8593-03 9.3386-02
2.0 2.0
300.0 1.0
2.1250-04 9.3386-02
2.0 2.0
300.0 1.0
2.1250-04 2.8593-03
2.0 2.0
3 0.1260000
1 1.10293
5 6.00302
41.09304
92.23805
5 6.00302
41.09304
92.23805


and 300 K 30% Void Fraction


1 1 0
0 0 0
132 128 122


300.0
3.0
0.0
1.4875-04
2.0015-03
6.5370-02
1.1652-02
4.2749-02
1.8321-02
2.1250-04
2.6173-02
2.0
2 .8593-03
2 .6173-02
2.0
2 .6173-02
9.3386-02
2.0
0.05200000
1.6646-02
9.3386-02
2 .6173-02
2.1250-04
9.3386-02
2.6173-02
2.1250-04


0 1 0
1 0 0
116 110 106


1.0-05
1.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.126
502.0

0.126
501.0

0.126
501.0


94 1 60


62 27


1.0
1.0
300.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
506 .0

0.0
506.0

0.0
502.0


0.05200000

40.00005 6.1069-02
92.23505 2.8593-03

40.00005 6.1069-02
92.23505 2.8593-03


0.0
0.0
0.0
0.0
0.0
0.0
5.0
607.0

5.0
607.0

5.0
506.0






















APPENDIX B

SAMPLE OF VENTURE OF INPUT FILE


=CONTROLl
HONEYCOMB 2D K-EFF CALCULATION WITH GRAPHITE REFLECTOR
36000 0 0 0 0 0 0 0 0 0 0 0 0 0 0
1 2 6 6 2 7 0 0


END
INPUT PROCESSOR
OV ISOTXS *COMBINE VERS* 523
ID 16 7 2 12


1
1 1 1 1


2D Honeycomb Core For 1.2 Density and 300 K 30% Void Fraction
* IIX101 IIX612 IIX102 IIX103 IIX104 IIX105 IIX111


1.39857E-01
1.40095E-04
0.00000E+00
3.07115E+04
7.97189E+02
1.48407E+01
8. 20850E+05
4.53999E+02
2.00000E-01


6.20672E-01
3.60562E-05
0.00000E+00
1.70585E+04
4.24483E+02
8.74660E+00
1.11090E+05
1.01301E+02
1.50000E-02


2.23873E-01
3.80280E-06
0.00000E+00
7.82645E+03
2.01742E+02
4.00262E+00
3.18278E+04
2.26033E+01
1.00000E-03


0 3 6 9 12 15
4D IIX101 IIX101 IIX101
0.10000E+01 0.10000E+01 0.10000E+01
0 0 1 0 0 0
2 3 4 5 6 7
14 15 15 14 13 3
3 3 3 3 3 3
5D 2.91167E-01 4.21786E-01 7.07382E


1.31318E-02
4.00872E-07
0.00000E+00
3.38953E+03
9.60646E+01
1.24770E+00
9.11882E+03
8.31529E+00


0.10000E+01
0 0
8 9
3 3


2.08408E-03 2.00986E-04
3.66924E-08 9.42796E-09


1.79781E+03
5.13288E+01
1.69046E+07
5.53084E+03
1.86000E+00




0.10000E+01


1.16254E+03
2.69100E+01
3.67879E+06
2.03468E+03
7.00000E-01




0.10000E+01
0 0
12 13
3 3


3 2 1
-01 7.47619E-01 6.53348E-01


6.87263E-01
6.85895E-01
5.65435E-01
1.01428E+00
1.47113E+00
4.63098E-03
4.48518E-02
4.35060E-01
6.51645E-03
3.17261E-02
2.61036E+00
2.43670E+00
2.43670E+00


6.69527E-01
8.12137E-01
9.59158E-01
1.05079E+00
1.97417E+00
9.38866E-03
7.77587E-02
2.45743E-03
9.52371E-03
8.72398E-02
2.47166E+00
2.43670E+00
2.43669E+00


6.65650E-01
9.60103E-01
9.94090E-01
1.07224E+00
4.35691E+00
2.03812E-02
4.70931E-02
2.51717E-03
1.84402E-02
2.35648E-01
2.44050E+00
2.43671E+00
2.43670E+00


6.78560E-01
1.40817E+00
9.39510E-01
1.13719E+00
2.11920E-04
2.46665E-02
2.30792E-02
2.51903E-03
3.60533E-02
5.76207E-01
2.43677E+00
2.43670E+00


6.91008E-01
3.73018E+00
1.02516E+00
1.03746E+00
9.57260E-04
3.28576E-02
5.42110E-02
3.48270E-03
6.88852E-02
2.16030E+00
2.43669E+00
2.43670E+00


7.26561E-01
3.94370E-01
1.00856E+00
1.23348E+00
2.24742E-03
5.47286E-02
1.22472E-01
4.76894E-03
9.92453E-02
3.10947E+00
2.43670E+00
2.43670E+00


7D 0.OOOOOE+00 0.OOOOOE+00 2.15636E-01 0.OOOOOE+00 0.00000E+00


4.49882E-01
3.32234E-02
1.31382E-03
1.40406E-03
2.17983E-02
6.31936E-01
2.94821E-05
4.17325E-02
0.OOOOOE+00
2.07766E-03


1.41256E-01
0.OOOOOE+00
0.OOOOOE+00
1.94716E-04
2.50673E-03
3.32305E-01
0.OOOOOE+00
9.58843E-03
6.92078E-01
2.36714E-04


0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
2.10249E-04
9.23050E-02
0.OOOOOE+00
1.07453E-03
2.17925E-01
2.02960E-05


0.OOOOOE+00
7.55515E-01
6.46761E-01
0.OOOOOE+00
3.02556E-05
2.12380E-02
6.91795E-01
9.09602E-05
5.06183E-02
2.97428E-06


8.58414E-01
7.37780E-02
1.75167E-01
5.34088E-01
0.OOOOOE+00
2.42966E-03
2.77410E-01
1.33297E-05
2.28814E-02
O.0000OOOOOE+00


1.03881E-01
6.26448E-03
1.58841E-02
1.32694E-01
0.OOOOOE+00
2.01661E-04
1.02548E-01
0.OOOOOE+00
9.28198E-03
0.OOOOOE+00













6.94815E-01
4.59515E-04
6.22168E-01
3.62629E-04
8.86146E-04
8.91239E-04
5.44740E-08
1.19863E-02
6.83289E-06
9.15943E-01
2.54995E-04
2.22031E-08
6.52501E-03
4.72877E-06
2.17022E-03
1.98112E-06
1.30020E-01
O.0000OOOOOE+00
1.63034E-01
1.88050E-01
O.0000OOOOOE+00
1.48536E-06
5.95727E-03
2.21908E-01
3.85403E-06
1.50102E-02
1.88083E-07
1.60778E-03
8.07323E-08
1.07609E-03
1.00198E-07
2.32302E-02
2.13899E-06
2.13201E-01
1.36291E-06
6.65961E-09
3.26143E-03
1.20077E-06
6.19474E-02
2.17231E-07
1.03806E-01
-5.25212E-06
1.32802E-08


2.15048E-01
5.28181E-05
1.77490E-01
8.34275E-05
6.81223E-01
4.02875E-04
2.68726E-11
2.65822E-03
7.91724E-07
2.52734E-01
6.94345E-05
7.85862E-01
1.91160E-03
1.07837E-06
1.90265E-03
8.27622E-07
0.OOOOOE+00
2.21249E-01
2.34143E-02
7.74192E-02
1.40361E-01
0.OOOOOE+00
2.87721E-04
1.26886E-01
5.61095E-07
4.54466E-03
0.OOOOOE+00
4.91087E-04
0.OOOOOE+00
1.51243E-04
2.78309E-08
2.54803E-03
3.96869E-07
8.66277E-02
2.23846E-06
2.68353E-06
5.38549E-04
4.83104E-07
6.25830E-03
5.24664E-06
4.27879E-03-
4.19772E-06-


4.14808E-02
4.52865E-06
3.34950E-02
9.58944E-06
2.72429E-01
1.63952E-04
3.98034E-03
5.91589E-04
7.16227E-08
6.56086E-02
3.13944E-05
1.20194E+00
4.23940E-04
9.28938E-08
5.11420E-04
2.79288E-07
0.OOOOOE+00
1.87457E-02
1.01513E-03
4.25216E-03
5.56324E-02
0.OOOOOE+00
1.16850E-05
4.27459E-02
0.OOOOOE+00
1.29297E-03
0.OOOOOE+00
1.42633E-04
0.OOOOOE+00
4.96891E-05
0.OOOOOE+00
2.83632E-04
8.00174E-08
1.29545E-02
1.43675E-06
9.55129E-03
5.79416E-05
1.03444E-07
4.27188E-03
2.09236E-06
3.92450E-04-
4.72511E-07


4D IIX612 IIX612 IIX612
0.10000E+01 0.10000E+01 0.10000E+01


0 0 1 0
2 3 4 5
L4 15 15 14 1
3 3 3 3


1.12724E-02
6.63653E-07
7.51555E-03
8.22202E-07
6.69872E-02
3.77193E-05
7.98617E-01
1.61088E-04
8.81551E-09
1.76352E-02
1.27805E-05
2.52806E-01
9.43483E-05
9.75229E-01
1.49828E-04
1.54725E-08
1.52975E-01
1.85729E-03
7.89299E-05
1.62135E-04
8.54040E-03
1.85874E-01
1.24821E-06
1.20640E-02
O.0000OOOOOE+00
1.68901E-04
2.28847E-01
2.23478E-05
1.91637E-01
1.66536E-05
6.51739E-04
4.53433E-05
2.25148E-08
2.19106E-03
6.33110E-07
2.52947E-01
8.66390E-06
1.37613E-08
5.42022E-04
1.05126E-06
-2.06118E-04
1.65801E-06


5.02733E-03 2.00424E-03
0.OOOOOE+00 0.OOOOOE+00


1.98073E-03
1.20490E-07
1.51276E-02
4.33558E-06
1.85635E-01
7.28351E-05
4.57695E-04
5.16650E-03
2.94521E-06
6.87553E-02
2.56908E-05
5.41861E-02
3.32277E-05
0.OOOOOE+00
6.50553E-03
O.0000OOOOOE+00
0.OOOOOE+00
1.35017E-05
4.09836E-04
1.34555E-01
0. OOOOOE+00
1.54917E-03
2.25937E-01
1.01034E-05
9.75064E-02
2.09192E-06
8.15541E-02
3.64501E-06
2.20920E-01
1.72785E-05
9.18040E-12
2.72703E-04
1.39096E-07
1.03956E-01
4.73640E-06
1.37503E-01
7.62339E-05
3.98716E-07
6.60778E-05
5.30555E-07


0.10000E+01 0.10000E+01


0 0 0 0
6 7 8 9
.3 3 3 3


3 3 3


8.91079E-04
0.OOOOOE+00
3.31809E-03
3.71734E-07
4.09136E-02
2.96507E-05
1.93630E-02
1.14578E-03
3.41236E-07
2.42752E-02
1.16159E-05
8.54433E-03
7.39487E-06
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
1.58265E-05
4.67778E-02
0.OOOOOE+00
7.64682E-05
9.95494E-02
8.61619E-07
1.15777E-02
3.05933E-07
9.81259E-03
5.36155E-07
1.28055E-01
7.03466E-06
2.05108E-03
3.91976E-05
3.14933E-08
2.45629E-02
2.25556E-06
2.78506E-01
1.24614E-06
4.61657E-08
9.12170E-07
1.90819E-07



0.10000E+01
0 0
12 13
3 3


2 1


5D 1.22365E+00 1.96254E+00 3.31743E+00 4.22386E+00 4.39634E+00


4.44446E+00
4.47384E+00
2.15387E+00
4.73403E+00
4.79936E+00
9.38312E-07
7.78379E-05
5.92450E-03
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00


4.45806E+00
4.30396E+00
3.65655E+00
4.73765E+00
4.80872E+00
1.04431E-06
1.45624E-04
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


4.46875E+00
4.55619E+00
4.51508E+00
4.73893E+00
4.14754E+00
6.04943E-06
2.78029E-04
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


4.47217E+00
4.71162E+00
4.66978E+00
4.73923E+00
8.25650E-03
1.25627E-05
4.98092E-04
O.0000OOOOOE+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00


4.47338E+00
4. 33193E+00
4.70830E+00
4.73941E+00
5.09843E-06
1.85818E-05
8.45129E-04
O.0000OOOOOE+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00


4.47366E+00
1.61297E+00
4.72270E+00
4.56521E+00
9.91359E-07
3.70724E-05
1.84679E-03
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00













7D 0.OOOOOE+00 0.OOOOOE+00 1.01636E+00 0.OOOOOE+00 0.OOOOOE+00


1.80422E+00
1.74498E-02
4.06860E-04
0.00000E+00
0.00000E+00
4.00150E+00
0.00000E+00
0.00000E+00
0.OOOOOE+00
0.00000E+00
4.31615E+00
0.00000E+00
4.10069E+00
0.00000E+00
8.95416E-03
0.00000E+00
0.00000E+00
0.00000E+00
0.00000E+00
4.42786E+00
0.00000E+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
4.12132E-07
0.OOOOOE+00
5.26686E-01
O.0000OOOOOE+00
4.49371E-01
4.39213E-01
0.OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00
4.05245E-01
0.OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00
0.OOOOOE+00
4.16516E-01
O.0000OOOOOE+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
-6.96530E-02
O.0000OOOOOE+00
-1.37998E-01
0.OOOOOE+00
0.OOOOOE+00


5.70496E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
1.49674E+00
0.OOOOOE+00
0.OOOOOE+00
4.29996E+00
0.OOOOOE+00
4.37652E-01
0.OOOOOE+00
4.22702E-01
0.OOOOOE+00
4.25718E+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
6.08029E-01
0.OOOOOE+00
7.64150E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
3.89450E-01-
5.03375E-02
1.58154E-01
7.04804E-01-
0.OOOOOE+00
0.OOOOOE+00
2.11896E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
1.45539E-01
0.OOOOOE+00
2.29141E-05
0.OOOOOE+00
0.OOOOOE+00
3.71809E-04
0.OOOOOE+00
2.30856E-03-
0.OOOOOE+00


0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
4.61129E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
6.38394E-01
0.OOOOOE+00
4.08233E-02
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
4.65391E+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
6.07682E-02
0.OOOOOE+00-
0.OOOOOE+00
1.65774E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
9.43144E-04
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
1.19039E-04-
0.OOOOOE+00


4D IIX102 IIX102 IIX102
0.10000E+01 0.10000E+01 0.10000E+01
0 0 1 0 0 0
2 3 4 5 6 7
14 15 15 14 13 3
3 3 3 3 3 3


0.OOOOOE+00
4.00892E+00
4.12206E+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
4.27288E+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
3.94706E+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00
3.28940E-01
0.OOOOOE+00
3.37729E+00
O.0000OOOOOE+00
0.OOOOOE+00
2.52107E-01
7.51912E-04
5.17870E-05
0.OOOOOE+00
0.OOOOOE+00
4.76539E-01
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
3.88630E-01
0.OOOOOE+00
4.53645E-01
0.OOOOOE+00
5.37337E-03
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
3.02245E-01
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00
1.20363E-07
0.OOOOOE+00



0.10000E+01
0 0


3.43684E+00
2.19706E-01
5.06161E-01
3.21155E+00
0.OOOOOE+00
0.OOOOOE+00
7.21186E-01
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
4.81949E-01
0.OOOOOE+00
1.77696E-04
O.0000OOOOOE+00
O.0000OOOOOE+00
6.69182E-04
0.OOOOOE+00
2.79854E-02
O.0000OOOOOE+00
0.OOOOOE+00
-1.38066E-01
O.0000OOOOOE+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
-4.40966E-01
O.0000OOOOOE+00
0.OOOOOE+00
3.94947E-01
O.0000OOOOOE+00
-1.29465E-01
0.OOOOOE+00
-1.23080E-01
0.OOOOOE+00
4.11105E-01
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
O.0000OOOOOE+00
-1.60266E-01
0.OOOOOE+00
-4.63623E-02
O.0000OOOOOE+00
O.0000OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


3.49646E-01
0.OOOOOE+00
0.OOOOOE+00
5.47717E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
1.24973E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
8.95035E-04
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
1.39964E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
1.88081E-01
0.OOOOOE+00
1.07050E-02
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
9.84657E-02
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


0.10000E+01 0.10000E+01
1 1 0 0
10 11 12 13
3 3 3 3


2 1


5D 2.75721E-01 3.98911E-01 6.83728E-01 6.80373E-01 5.73521E-01
6.16937E-01 5.92466E-01 5.92171E-01 6.12568E-01 6.26006E-01 6.77167E-01
6.09009E-01 7.51343E-01 8.93864E-01 1.29291E+00 3.93436E+00 3.74151E-01













5.24194E-01
7.36083E-01
1.15612E+00
4.79792E-03
4.99552E-02
4.91290E-01
7.60045E-03
3.68131E-02
2.60629E+00
2.43670E+00
2.43670E+00


8.58935E-01
7.74267E-01
1.62504E+00
9.66885E-03
9.14190E-02
2.86353E-03
1.10620E-02
9.44929E-02
2.47060E+00
2.43670E+00
2.43670E+00


7.88695E-01
7.96594E-01
4.07720E+00
2.10753E-02
5.50040E-02
2.93199E-03
2.10943E-02
2.52377E-01
2.44056E+00
2.43670E+00
2.43670E+00


6.81796E-01
8.75851E-01
2.08240E-04
2.55332E-02
2.43161E-02
2.95260E-03
4.15553E-02
6.15283E-01
2.43676E+00
2.43669E+00


7.51245E-01
7.60457E-01
1.00407E-03
3.59450E-02
5.33620E-02
4.05660E-03
7.80938E-02
2.53876E+00
2.43670E+00
2. 43670E+00


7.29489E-01
9.36932E-01
2.35373E-03
6.05857E-02
1.26914E-01
5.53695E-03
1.13471E-01
3.10694E+00
2.43670E+00
2.43670E+00


7D 0.OOOOOE+00 0.OOOOOE+00 2.12818E-01 0.OOOOOE+00 0.OOOOOE+00


4.35913E-01
2.98131E-02
9.11882E-04
5.79882E-04
8.07552E-03
5.36155E-01
1.10878E-05
1.53942E-02
O.0000OOOOOE+00
7.69112E-04
5.60996E-01
1.70150E-04
5.24359E-01
1.33764E-04
8.41321E-04
3.30206E-04
2.04868E-08
4.25878E-03
2.53013E-06
7.47002E-01
9.25517E-05
8.68663E-09
2.39352E-03
1.74433E-06
7.79023E-04
7.33257E-07
1.26813E-01
0.OOOOOE+00
8.59632E-02
9.05235E-02
O.0000OOOOOE+00
5.59292E-07
2.21575E-03
1.02273E-01
1.48940E-06
5.52305E-03
7.07442E-08
5.91661E-04
3.03618E-08
3.86523E-04
3.83343E-08
7.98745E-03
7.98847E-07
1.00111E-01
5.31447E-07
2.51018E-09-
1.17922E-03
4.45865E-07
1.72108E-02
6.58751E-07
3.49349E-02


1.27432E-01
0.OOOOOE+00
0.OOOOOE+00
7.54805E-05
9.77826E-04
1.90903E-01
0.OOOOOE+00
3.55042E-03
5.60519E-01
9.22513E-05
9.26291E-02
2.05841E-05
7.69169E-02
3.08917E-05
5.45147E-01
1.50913E-04
1.28722E-11
9.53254E-04
3.08467E-07
1.11445E-01
2.57257E-05
3.27465E-01
6.79202E-04
3.99152E-07
7.08616E-04
3.09947E-07
0.OOOOOE+00
1.70367E-01
6.29044E-03
2.14742E-02
8.46841E-02
0.OOOOOE+00
1.12895E-04
3.78222E-02
2.11133E-07
1.70315E-03
0.OOOOOE+00
1.84040E-04
0.OOOOOE+00
5.56877E-05
1.04663E-08
8.96974E-04
1.52823E-07
2.60626E-02
8.39288E-07
1.93416E-06
1.85211E-04
1.80548E-07
2.22238E-03
1.93258E-06
1.06348E-03-


0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
8.24617E-05
3.40499E-02
0.OOOOOE+00
4.18898E-04
9.63820E-02
7.82572E-06
1.50556E-02
1.74615E-06
1.20214E-02
3.73715E-06
1.22544E-01
6.04775E-05
4.08917E-03
2.14720E-04
2.75836E-08
2.44350E-02
1.17600E-05
8.48473E-01
1.52028E-04
3.65997E-08
1.87600E-04
1.02500E-07
0.OOOOOE+00
4.13169E-03
3.78213E-04
1.66853E-03
1.35215E-02
0.OOOOOE+00
4.52192E-06
1.60193E-02
0.OOOOOE+00
4.74929E-04
0.OOOOOE+00
5.24391E-05
0.OOOOOE+00
1.86226E-05
0.OOOOOE+00
1.01953E-04
3.06049E-08
4.68516E-03
5.34383E-07
4.55370E-03
2.03517E-05
3.97802E-08
1.59246E-03
7.84339E-07
1.56298E-04-


O.0000OOOOOE+00
6.72152E-01
5.41676E-01
0.OOOOOE+00
1.13787E-05
7.86598E-03
5.63331E-01
3.50724E-05
1.87542E-02
1.11858E-06
4.17599E-03
2.49589E-07
2.72705E-03
3.17024E-07
2.38049E-02
1.39667E-05
6.80158E-01
5.96837E-05
3.31965E-09
6.46898E-03
4.71440E-06
9.63388E-02
3.42441E-05
7.19510E-01
5.32348E-05
5.59581E-09
1.38887E-01
7.32036E-04
2.75771E-05
6.25284E-05
3.17648E-03
9.14018E-02
4.69893E-07
4.43076E-03
O.0000OOOOOE+00
6.28307E-05
1.05085E-01
8.32334E-06
9.22148E-02
6.13886E-06
5.58687E-04
1.67274E-05
8.46710E-09
7.55098E-04
2.36648E-07
1.12076E-01
3.40551E-06
5.37693E-09
1.95662E-04
3.90120E-07
-7.24831E-05


8.03492E-01
4.14650E-02
8.72087E-02
4.82270E-01
O.0000OOOOOE+00
9.47227E-04
1.32649E-01
5.01309E-06
8.57114E-03
O.0000OOOOOE+00
1.88313E-03
0.OOOOOE+00
7.33726E-04
4.53144E-08
5.42833E-03
1.68964E-06
8.93085E-02
2.72833E-05
1.79822E-04
1.83568E-03
1.09057E-06
2.48993E-02
9.51852E-06
1.80895E-02
1.19157E-05
O.0000OOOOOE+00
-3.57565E-03
0.OOOOOE+00
0.OOOOOE+00
5.08485E-06
1.60816E-04
3.04059E-02
0.OOOOOE+00
5.76234E-04
1.03828E-01
3.94356E-06
2.95136E-02
8.10766E-07
2.38715E-02
1.35974E-06
1.01091E-01
6.47629E-06
4.31002E-12
9.67277E-05
5.34817E-08
3.12105E-02
1.75100E-06
4.97504E-02
2.58138E-05-
1.48964E-07
2.45936E-05-


8.01556E-02
3.40410E-03
6.20892E-03
7.10962E-02
0.OOOOOE+00
7.80836E-05
3.84133E-02
0.OOOOOE+00
3.42330E-03
0.OOOOOE+00
7.39200E-04
0.OOOOOE+00
3.33789E-04
0.OOOOOE+00
1.20339E-03
1.43333E-07
1.50080E-02
1.09374E-05
1.62781E-02
4.10885E-04
1.32952E-07
9.04097E-03
4.35121E-06
2.94661E-03
2.68400E-06
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
6.10710E-06
1.71793E-02
0.OOOOOE+00
2.99748E-05
3.02611E-02
3.31142E-07
4.15750E-03
1.17170E-07
3.45305E-03
2.06814E-07
3.96542E-02
2.60207E-06
1.56281E-03
1.31637E-05
1.20261E-08
9.15714E-03
8.45554E-07
1.11488E-01
6.78500E-07
1.81083E-08
4.50854E-07












-1.96142E-06-1.56701E-06 3.47222E-08 6.08794E-07 1.98846E-07 7.03099E-08
4.90324E-09
4D IIX103 IIX103 IIX103
0.10000E+01 0.10000E+01 0.10000E+01 0.10000E+01 0.10000E+01 0.10000E+01
0 0 1 0 0 0 0 0 1 1 0 0
2 3 4 5 6 7 8 9 10 11 12 13
14 15 15 14 13 3 3 3 3 3 3 3
3 3 3 3 3 3 3 2 1
5D 2.73567E-01 3.95733E-01 6.82090E-01 6.70025E-01 5.63106E-01


6.12001E-01
6.06710E-01
5.17881E-01
6.83099E-01
1.11251E+00
4.97580E-03
5.51299E-02
5.56860E-01
8.68256E-03
4.18833E-02
2.60516E+00
2.43670E+00
2.43670E+00


5.85521E-01
7.57044E-01
8.40890E-01
7.24775E-01
1.62495E+00
9.95592E-03
1.04263E-01
3.27171E-03
1.26030E-02
1.02791E-01
2.47012E+00
2.43670E+00
2.43671E+00


5.89350E-01
9.11654E-01
7.47599E-01
7.50116E-01
4.37851E+00
2.16449E-02
6.26717E-02
3.34930E-03
2.37591E-02
2.76093E-01
2.44058E+00
2.43669E+00
2.43670E+00


6.15722E-01
1.34237E+00
6.29142E-01
8.42546E-01
2.01170E-04
2.61932E-02
2.62760E-02
3.38190E-03
4.70202E-02
6.85265E-01
2. 43677E+00
2.43671E+00


6.30805E-01 6.94433E-01
4.60746E+00 3.72451E-01


6.95597E-01
7.12255E-01
1.03756E-03
3.82067E-02
5.57840E-02
4.63275E-03
8.72871E-02
2.93245E+00
2.43670E+00
2.43670E+00


6.73395E-01
8.82512E-01
2.44839E-03
6.51498E-02
1.39074E-01
6.30748E-03
1.27634E-01
3.10639E+00
2.43670E+00
2.43669E+00


7D 0.OOOOOE+00 0.OOOOOE+00 2.14047E-01 0.OOOOOE+00 0.OOOOOE+00


4.35238E-01
2.92535E-02
8.29974E-04
3.83523E-04
4.94371E-03
5.21316E-01
6.82756E-06
9.36825E-03
0.OOOOOE+00
4.70477E-04
5.36770E-01
1.04097E-04
5.09001E-01
8.14021E-05
8.82469E-04
2.01485E-04
1.26153E-08
2.53266E-03
1.54794E-06
7.12817E-01
5.56007E-05
5.40830E-09
1.45474E-03
1.06151E-06
4.65578E-04
4.47100E-07
1.27406E-01
O.0000OOOOOE+00
6.84590E-02
6.78705E-02
O.0000OOOOOE+00
3.44458E-07
1.35386E-03
7.41303E-02
9.24418E-07
3.35346E-03
4.35611E-08
3.59275E-04
1.86949E-08
2.29840E-04


1.24782E-01
0.OOOOOE+00
0.OOOOOE+00
4.80822E-05
6.13340E-04
1.58480E-01
0.OOOOOE+00
2.17223E-03
5.37937E-01
5.78142E-05
6.33430E-02
1.29001E-05
5.27104E-02
1.88994E-05
5.19600E-01
9.27591E-05
8.52531E-12
5.68567E-04
1.93294E-07
7.74002E-02
1.56974E-05
2.21544E-01
4.03916E-04
2.44160E-07
4.34665E-04
1.90463E-07
0.OOOOOE+00
1.59013E-01
2.06602E-03
8.65663E-03
7.21661E-02
0.OOOOOE+00
7.10643E-05
1.77100E-02
1.30017E-07
1.04680E-03
0.OOOOOE+00
1.13116E-04
0.OOOOOE+00
3.38287E-05


0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
5.19943E-05
2.07219E-02
0.OOOOOE+00
2.62571E-04
6.72868E-02
4.85305E-06
9.04472E-03
1.08286E-06
7.17431E-03
2.34208E-06
8.70255E-02
3.68035E-05
4.39874E-03
1.28994E-04
1.71002E-08
1.49884E-02
7.22836E-06
7.73903E-01
9.06767E-05
2.30542E-08
1.14020E-04
6.21589E-08
0.OOOOOE+00
5.60932E-04
2.25082E-04
1.05029E-03
4.10005E-03
0.OOOOOE+00
2.80451E-06
9.84582E-03
0.OOOOOE+00
2.87643E-04
0.OOOOOE+00
3.17822E-05
0.OOOOOE+00
1.14473E-05


0.OOOOOE+00
6.58501E-01
5.23854E-01
0.OOOOOE+00
7.00669E-06
4.81388E-03
5.42234E-01
2.17499E-05
1.14434E-02
6.88792E-07
2.54791E-03
1.53691E-07
1.63794E-03
1.96600E-07
1.41583E-02
8.54480E-06
6.59723E-01
3.64180E-05
2.04474E-09
3.93173E-03
2.86895E-06
6.16686E-02
2.05723E-05
6.67537E-01
3.16583E-05
3.38131E-09
1.36590E-01
4.71462E-04
1.56297E-05
3.85853E-05
1.94086E-03
6.93031E-02
2.89387E-07
2.68325E-03
O.0000OOOOOE+00
3.83965E-05
7.52669E-02
5.09148E-06
6.83411E-02
3.72842E-06


7.95288E-01
3.43241E-02
6.69550E-02
4.76428E-01
0.OOOOOE+00
5.93728E-04
9.85837E-02
3.08693E-06
5.26829E-03
O.0000OOOOOE+00
1.15744E-03
0.OOOOOE+00
4.47643E-04
2.79034E-08
3.23914E-03
1.05890E-06
6.71313E-02
1.67698E-05
1.15992E-04
1.09167E-03
6.67215E-07
1.49740E-02
5.80804E-06
1.10811E-02
7.10709E-06
0.OOOOOE+00
-5.98646E-03
O.0000OOOOOE+00
0.OOOOOE+00
3.13179E-06
1.01235E-04
6.20342E-03
0.OOOOOE+00
3.52105E-04
7.47724E-02
2.47583E-06
1.48035E-02
5.07182E-07
1.17726E-02
8.32880E-07


7.50158E-02
2.72831E-03
3.90384E-03
5.62732E-02
0.OOOOOE+00
4.86271E-05
2.36109E-02
0.OOOOOE+00
2.08300E-03
0.OOOOOE+00
4.49791E-04
0.OOOOOE+00
2.05165E-04
0.OOOOOE+00
7.22522E-04
8.88868E-08
9.12161E-03
6.65597E-06
1.56225E-02
2.45072E-04
8.33114E-08
5.54573E-03
2.67449E-06
1.74383E-03
1.61242E-06
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
3.77314E-06
1.04033E-02
0.OOOOOE+00
1.88596E-05
1.49462E-02
2.05206E-07
2.47162E-03
7.25366E-08
2.03026E-03
1.29060E-07













6.44447E
5.27525E
9.52827E
1.21656E
5.16322E
1.77060E
1.07798E
1.10762E
1.31602E
1.17428E
5.32578E
9.61411E


0.OOOOOE+00
6.06607E-05
1.89394E-08
2.82605E-03
3.26831E-07
3.09439E-03
1.19490E-05
2.47857E-08
9.78108E-04
4.82317E-07
9.91385E-05-
1.15695E-07


2.97291E-09
4D IIX104 IIX104 IIX104
0.10000E+01 0.10000E+01 0.10000E+01
0 0 1 0 0 0
2 3 4 5 6 7
14 15 15 14 13 3
3 3 3 3 3 3


5. 69781E
1. 01755E
5.21348E
4. 40124E
1.45198E
7.82564E
2. 16236E
3.34730E
1. 17897E
2. 38178E
-4.26457E
3.69090E


7.34873E-
3. 98166E-
2.85248E-
5. 72125E-
3. 33198E-
1.55203E-
1.06675E-
2.95767E-
1.48627E-
9. 13547E-
1.50963E-
1.22234E-


2.02760E
1.58463E
1.50740E
7.40537E
7.43872E
5.62456E
5.20007E
7.28819E
5.05987E
1.13913E
3.13342E
4.26960E


0.10000E+01 0.10000E+01 0.10000E+01
0 0 1 1 0 0
8 9 10 11 12 13
3 3 3 3 3 3
3 2 1


5D 2.69971E-01 3.90173E-01 6.74511E-01 6.54718E-01 5.47725E-01


5.98969E-01
5.82286E-01
5.09237E-01
6.42397E-01
1.02611E+00
4.78409E-03
4.88582E-02
4.95080E-01
7.59466E-03
3.68493E-02
2. 60459E+00
2. 43671E+00
2.43670E+00


5.70785E-01
7.35730E-01
8.24438E-01
6.78097E-01
1.47098E+00
9.60506E-03
9.28830E-02
2.86227E-03
1.10062E-02
8.96144E-02
2.46985E+00
2.43670E+00
2.43670E+00


5.74358E-01
8.78261E-01
7.18071E-01
6.93954E-01
3.87451E+00
2.11779E-02
5.59243E-02
2.92987E-03
2.06503E-02
2.39205E-01
2.44059E+00
2.43670E+00
2.43670E+00


5.98695E-01
1.25777E+00
5.93373E-01
7.77529E-01
2.09890E-04
2.56600E-02
2.35096E-02
2.96296E-03
4.10289E-02
5.95793E-01
2.43678E+00
2. 43671E+00


6.07001E-01 6.67859E-01
4.18551E+00 3.66113E-01


6.57567E-01
6.61996E-01
1.01246E-03
3.74701E-02
4.89240E-02
4.05229E-03
7.63468E-02
2.57341E+00
2.43670E+00
2. 43670E+00


6.34373E-01
8.26771E-01
2.37430E-03
6.29701E-02
1.22832E-01
5.50764E-03
1.12794E-01
3.10603E+00
2.43669E+00
2.43670E+00


7D 0.OOOOOE+00 0.OOOOOE+00 2.11071E-01 0.OOOOOE+00 0.OOOOOE+00


4.30550E-01
2.85721E-02
7.72543E-04
2.95468E-04
3.56143E-03
5.04521E-01
4.93316E-06
6.71891E-03
O.0000OOOOOE+00
3.38803E-04
5.12863E-01
7.49683E-05
4.89616E-01
5.83811E-05
8.62538E-04
1.44789E-04
9.11499E-09
1.81515E-03
1.11479E-06
6.84734E-01
3.96972E-05
3.93008E-09
1.04702E-03
7.61313E-07
3.34788E-04
3.21151E-07
1.25177E-01
O.0000OOOOOE+00
5.98137E-02


1.22577E-01
0.OOOOOE+00
0.OOOOOE+00
3.54880E-05
4.48085E-04
1.42336E-01
0.OOOOOE+00
1.56442E-03
5.15299E-01
4.22010E-05
5.07132E-02
9.41633E-06
4.28286E-02
1.36109E-05
4.97519E-01
6.69460E-05
6.27202E-12
4.05852E-04
1.41084E-07
6.34958E-02
1.12803E-05
1.73256E-01
2.89485E-04
1.75825E-07
3.12723E-04
1.37440E-07
0.OOOOOE+00
1.52511E-01-
1.71232E-04


0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
3.83263E-05
1.48619E-02
0.OOOOOE+00
1.91684E-04
5.43692E-02
3.51926E-06
6.45766E-03
7.85254E-07
5.12227E-03
1.70959E-06
7.17122E-02
2.63953E-05
4.35097E-03
9.20976E-05
1.23983E-08
1.07835E-02
5.21685E-06
7.29282E-01
6.47264E-05
1.68780E-08
8.20639E-05
4.44812E-08
0.OOOOOE+00
9.85377E-04
1.56172E-04


0.OOOOOE+00
6.42769E-01
5.05829E-01
O.0000OOOOOE+00
5.06259E-06
3.46737E-03
5.21617E-01
1.57722E-05
8.22337E-03
4.97677E-07
1.83086E-03
1.11047E-07
1.16931E-03
1.42567E-07
1.01474E-02
6.15377E-06
6.38169E-01
2.61704E-05
1.47768E-09
2.82979E-03
2.05760E-06
4.76440E-02
1.46880E-05
6.32672E-01
2.26894E-05
2.41982E-09
1.34116E-01
3.54542E-04
1.03753E-05


7.84231E-01
3.08862E-02
5.74375E-02
4.64546E-01
0.OOOOOE+00
4.33427E-04
8.26236E-02
2.23042E-06
3.80223E-03
0.OOOOOE+00
8.35331E-04
O.0000OOOOOE+00
3.21656E-04
2.01612E-08
2.31254E-03
7.72939E-07
5.66177E-02
1.21031E-05
8.71031E-05
7.82392E-04
4.80514E-07
1.07847E-02
4.17372E-06
8.23384E-03
5.07315E-06
0.OOOOOE+00
-6.92786E-03
O.0000OOOOOE+00
O.0000OOOOOE+00


7.19398E-02
2.41544E-03
2.85602E-03
4.89413E-02
0.OOOOOE+00
3.54113E-05
1.70404E-02
0.OOOOOE+00
1.49381E-03
0.OOOOOE+00
3.22566E-04
0.OOOOOE+00
1.48071E-04
0.OOOOOE+00
5.15722E-04
6.44576E-08
6.56511E-03
4.77364E-06
1.48438E-02
1.74936E-04
6.08085E-08
3.98991E-03
1.93023E-06
1.25479E-03
1.15122E-06
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


2.37246E-
4.64836E-
4.89784E-
7.29384E-
3. 35861E-
1.54632E-
7. 11193E-
2.72337E-
8. 41531E-
6.61845E-
2.03492E-
*1.20380E-













5.71125E-02
0.OOOOOE+00
2.48957E-07
9.75005E-04
6.08748E-02
6.70629E-07
2.40305E-03
3.14774E-08
2.57466E-04
1.35087E-08
1.63628E-04
1.71851E-08
3.31762E-03
3.53236E-07
6.00042E-02
2.46146E-07
1.11778E-09
5.11293E-04
1.95804E-07
5.13163E-03
5.66664E-07
1.37342E-02
-8.69059E-07
2.13395E-09


3.18672E-03
6.57931E-02
0.OOOOOE+00
5.20313E-05
9.17939E-03
9.39578E-08
7.55505E-04
0.OOOOOE+00
8.16398E-05
0.OOOOOE+00
2.42484E-05
4.65665E-09
3.75593E-04
6.93541E-08
6.15841E-03
3.72838E-07
1.69005E-06
7.69399E-05
7.99020E-08
9.41837E-04
8.41890E-07
3.50738E-04-
6.93685E-07


7.68982E-04
2.16514E-04
0.OOOOOE+00
2.03223E-06
7.10599E-03
0.OOOOOE+00
2.05743E-04
0.OOOOOE+00
2.27428E-05
0.OOOOOE+00
8.26242E-06
0.OOOOOE+00
4.31978E-05
1.37184E-08
2.03178E-03
2.35170E-07
2.30571E-03
8.50286E-06
1.80336E-08
7.02079E-04
3.48201E-07
7.29418E-05-
1.16011E-07


2.78100E-05
1.39774E-03
5.87729E-02
2.09146E-07
1.91914E-03
0.OOOOOE+00
2.76535E-05
6.10596E-02
3.66848E-06
5.71512E-02
2.67141E-06
5.46600E-04
7.29960E-06
3.76716E-09
3.14234E-04
1.04750E-07
6.23414E-02
1.58720E-06
2.43206E-09
8.47412E-05
1.71197E-07
-3.06386E-05
2.64260E-07


4D IIX105 IIX105 IIX105
0.10000E+01 0.10000E+01 0.10000E+01 0.10000E+01
0 0 1 0 0 0 0 0
2 3 4 5 6 7 8 9
14 15 15 14 13 3 3 3
3 3 3 3 3 3 3 2


2.26358E-06
7.41261E-05
-4.03649E-03
0.OOOOOE+00
2.53580E-04
6.09515E-02
1.80981E-06
8.81932E-03
3.69927E-07
6.88567E-03
6.00438E-07
6.07775E-02
2.87416E-06
2.07546E-12
4.08093E-05
2.42416E-08
9.01535E-03
7.65954E-07
2.05361E-02
1.05824E-05
6.58946E-08
1.08209E-05
8.82269E-08



0.10000E+01


0.OOOOOE+00
2.72305E-06
7.44060E-03
0.OOOOOE+00
1.38047E-05
8.56048E-03
1.48745E-07
1.75945E-03
5.25511E-08
1.44540E-03
9.39918E-08
1.19078E-02
1.13726E-06
1.39867E-03
5.11921E-06
5.38677E-09
4.03750E-03
3.75430E-07
5.54262E-02
3.84895E-07
8.33518E-09
2.31976E-07
3.05881E-08



0.10000E+01
0 0
12 13
3 3


5D 2.68971E-01 3.88643E-01 6.72951E-01 6.50192E-01 5.44008E-01


5.97483E-01
5.79356E-01
5.06645E-01
6.26729E-01
1.00227E+00
4.78136E-03
4.89331E-02
4.96630E-01
7.59092E-03
3.71597E-02
2.60427E+00
2.43670E+00
2.43670E+00


5.68500E-01
7.34854E-01
8.18514E-01
6.61823E-01
1.44414E+00
9.58464E-03
9.53150E-02
2.86205E-03
1.09849E-02
8.83986E-02
2.46968E+00
2.43670E+00
2.43670E+00


5.73375E-01
8.79591E-01
7.05794E-01
6.77055E-01
3.84452E+00
2.11962E-02
5.68413E-02
2.92946E-03
2.04996E-02
2.35931E-01
2.44060E+00
2.43670E+00
2.43670E+00


5.98854E-01
1.25948E+00
5.78058E-01
7.65505E-01
2.10170E-04
2.56807E-02
2.33314E-02
2.96539E-03
4.08579E-02
5.92218E-01
2.43677E+00
2.43670E+00


6.06182E-01 6.72428E-01
4.40412E+00 3.64715E-01


6.41400E-01
6.46118E-01
1.01405E-03
3.79114E-02
4.78620E-02
4.05144E-03
7.64879E-02
2.58410E+00
2.43670E+00
2.43670E+00


6.18057E-01
8.07170E-01
2.37914E-03
6.37081E-02
1.22105E-01
5.49826E-03
1.15064E-01
3.10586E+00
2.43670E+00
2.43670E+00


7D 0.00000E+00 0.00000E+00 2.10767E-01 0.00000E+00 0.00000E+00


4.29638E-01
2.83560E-02
7.48280E-04
2.45354E-04
2.78346E-03
4.99611E-01
3.86140E-06
5.22920E-03
0.OOOOOE+00
2.64657E-04
5.04953E-01
5.85642E-05
4.84543E-01
4.54364E-05
8.72175E-04
1.12806E-04
7.13470E-09
1.40195E-03


1.21733E-01
0.OOOOOE+00
0.OOOOOE+00
2.85236E-05
3.53329E-04
1.33637E-01
0.OOOOOE+00
1.22215E-03
5.07868E-01
3.32488E-05
4.31447E-02
7.41880E-06
3.65959E-02
1.06327E-05
4.89324E-01
5.23553E-05
4.99968E-12
3.13378E-04


0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
3.05470E-05
1.15670E-02
0.OOOOOE+00
1.51032E-04
4.67163E-02
2.76025E-06
4.99459E-03
6.15895E-07
3.95615E-03
1.34693E-06
6.23897E-02
2.05427E-05
4.45048E-03
7.12317E-05


0.OOOOOE+00
6.37662E-01
4.99881E-01
0.OOOOOE+00
3.96271E-06
2.70929E-03
5.15190E-01
1.23706E-05
6.40686E-03
3.89554E-07
1.42637E-03
8.69214E-08
9.04287E-04
1.11819E-07
7.83785E-03
4.80724E-06
6.30935E-01
2.03895E-05


7.80950E-01
2.90744E-02
5.22440E-02
4.61839E-01
0.OOOOOE+00
3.41502E-04
7.35509E-02
1.74585E-06
2.97354E-03
0.OOOOOE+00
6.53261E-04
0.OOOOOE+00
2.50585E-04
1.57811E-08
1.78596E-03
6.08973E-07
5.09969E-02
9.46525E-06


7.05025E-02
2.24130E-03
2.25629E-03
4.48123E-02
0.OOOOOE+00
2.78906E-05
1.33265E-02
0.OOOOOE+00
1.16253E-03
0.OOOOOE+00
2.51031E-04
0.OOOOOE+00
1.15799E-04
0.OOOOOE+00
3.98766E-04
5.05557E-08
5.11124E-03
3.71520E-06













8.70864E-07
6.73688E-01
3.07033E-05
3.08593E-09
8.15154E-04
5.92510E-07
2.59707E-04
2.50114E-07
1.24892E-01
0.00000E+00
5.52201E-02
5.11407E-02
0.OOOOOE+00
1.94886E-07
7.61183E-04
5.34117E-02
5.26126E-07
1.86742E-03
2.46390E-08
2.00088E-04
1.05739E-08
1.25949E-04
1.34710E-08
2.54060E-03
2.76101E-07
5.27406E-02
1.95176E-07
8.75066E-10
3.96849E-04
1.52661E-07
3.26039E-03
5.13651E-07
1.10449E-02
-6.79423E-07
1.66118E-09


1.11150E-07
5.49870E-02
8.78856E-06
1.46095E-01
2.23587E-04
1.37345E-07
2.44513E-04
1.07470E-07
0.OOOOOE+00
1.49348E-01-
9.50800E-04
5.95830E-05
6.24518E-02-
0.OOOOOE+00
4.10722E-05
4.39351E-03
7.35477E-08
5.90774E-04
0.OOOOOE+00
6.38393E-05
0.OOOOOE+00
1.88485E-05
3.64496E-09
2.88452E-04
5.45444E-08
2.72735E-03
2.91722E-07
1.64741E-06
5.89228E-05
6.24669E-08
7.26366E-04
6.54507E-07
2.41645E-04-
5.42228E-07


9.72341E-09
8.43148E-03
4.07985E-06
7.08583E-01
4.99785E-05
1.33221E-08
6.38904E-05
3.45573E-08
0.OOOOOE+00
1.89337E-03
1.16883E-04
6.06990E-04
1.95831E-03
0.OOOOOE+00
1.59219E-06
5.55656E-03
0.OOOOOE+00
1.59711E-04
0.OOOOOE+00
1.76609E-05
0.OOOOOE+00
6.46139E-06
0.OOOOOE+00
3.32609E-05
1.07532E-08
1.57710E-03
1.83476E-07
1.88256E-03
6.52531E-06
1.41791E-08
5.49346E-04
2.72370E-07
5.80885E-05-
1.16569E-07


4D IIX111 IIX111 IIX111
0.10000E+01 0.10000E+01 0.10000E+01
0 0 1 0 0 0
2 3 4 5 6 7
14 15 15 14 13 3
3 3 3 3 3 3


1.15674E-09
2.20312E-03
1.60138E-06
3.93631E-02
1.13602E-05
6.17621E-01
1.75244E-05
1.88238E-09
1.33305E-01
2.88760E-04
7.37780E-06
2.16670E-05
1.09121E-03
5.28982E-02
1.63719E-07
1.48968E-03
0.OOOOOE+00
2.15902E-05
5.30888E-02
2.86512E-06
5.07811E-02
2.07673E-06
5.48220E-04
5.67818E-06
2.94872E-09
2.40791E-04
8.18968E-08
5.34730E-02
1.26091E-06
1.90962E-09
6.57483E-05
1.33445E-07
-2.36556E-05
2.05196E-07


7.08951E-05
6.04289E-04
3.75372E-07
8.38609E-03
3.25177E-06
6.62958E-03
3.91723E-06
0.OOOOOE+00
-7.51217E-03
0.OOOOOE+00
0.OOOOOE+00
1.77197E-06
5.85170E-05
-9.97105E-03
0.OOOOOE+00
1.97973E-04
5.31903E-02
1.42718E-06
5.50835E-03
2.91311E-07
4.20661E-03
4.69166E-07
5.37217E-02
2.24791E-06
1.65082E-12
3.14186E-05
1.90596E-08
5.40723E-03
5.96298E-07
1.54909E-02
8.06824E-06
5.15104E-08
8.46604E-06
6.89966E-08


1.46033E-02
1.35077E-04
4.79069E-08
3.11965E-03
1.50954E-06
9.74110E-04
8.90396E-07
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
2.12454E-06
5.77547E-03
0.OOOOOE+00
1.08953E-05
5.04112E-03
1.16641E-07
1.35415E-03
4.11971E-08
1.10992E-03
7.39468E-08
7.34656E-03
8.85327E-07
1.37938E-03
3.81842E-06
4.22188E-09
3.15918E-03
2.93686E-07
4.56750E-02
3.21067E-07
6.57696E-09
1.89678E-07
2.37775E-08


0.10000E+01 0.10000E+01 0.10000E+01
0 0 1 1 0 0
8 9 10 11 12 13


3 3 3
2 1


3 3


5D 1.14128E+00 2.42341E+00 5.65482E+00 9.54370E+00 1.21217E+01


1.30080E+01
1.36637E+01
6.92896E+00
4.06159E+01
4.58987E+01
3.07598E-04
1.44125E-02
1.20474E+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


1.33072E+01
1.65586E+01
1.56413E+01
4.08585E+01
5.29746E+01
7.04138E-04
2.78769E-02
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


1.35174E+01
2.03107E+01
2.92173E+01
4.09124E+01
1.02559E+02
1.21110E-03
5.37950E-02
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


1.36014E+01
2. 84008E+01
3. 64600E+01
4.09259E+01
7.19337E-05
1.80584E-03
9.51230E-02
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


1.36244E+01
8.11204E+01
3.90892E+01
4.09515E+01
6.92285E-05
3.29920E-03
1.56746E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


1.36379E+01
3.33169E+00
3.99748E+01
4.28267E+01
1.03560E-04
6.87012E-03
3.29843E-01
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00


7D 0.OOOOOE+00 0.OOOOOE+00 6.91021E-01 0.OOOOOE+00 0.OOOOOE+00
2.56342E+00 2.04576E+00 0.OOOOOE+00 0.OOOOOE+00 8.47789E+00 3.77573E+00
5.14133E-01 0.OOOOOE+00 0.OOOOOE+00 1.30140E+01 5.11433E+00 4.21838E-01
5.75741E-02 0.OOOOOE+00 0.OOOOOE+00 1.66219E+01 1.15669E+01 1.46527E+00
1.20778E-01 1.65011E-02 0.OOOOOE+00 0.OOOOOE+00 8.41806E+00 7.80965E+00
1.82755E+00 2.31509E-01 1.86475E-02 2.60739E-03 0.OOOOOE+00 0.OOOOOE+00
1.56653E+01 1.93944E+01 7.60981E+00 1.78078E+00 2.24702E-01 1.80031E-02
2.54073E-03 0.OOOOOE+00 0.OOOOOE+00 2.16653E+01 1.88930E+01 8.76859E+00













3.44054E+00
0.OOOOOE+00
1.74139E-01
2.28537E+01
3.85341E-02
1.67332E+01
2.98963E-02
3.56149E-02
7.42242E-02
4.69450E-06
9.22457E-01
5.73012E-04
2.79193E+01
2.02022E-02
2.03049E-06
5.36356E-01
3.89861E-04
1.70851E-01
1.64570E-04
6.54227E-01
0.OOOOOE+00
1.08091E+01
1.39799E+01
0.OOOOOE+00
1.28231E-04
5.00857E-01
1.76868E+01
3.46181E-04
1.22873E+00
1.62120E-05
1.31654E-01
6.95740E-06
8.28723E-02
8.86364E-06
1.67167E+00
1.81669E-04
1.70742E+01
1.28422E-04
5.75777E-07-
2.61119E-01
1.00448E-04
4.16252E+00
3.37973E-04
9.21918E+00
-4.47048E-04-
1.09303E-06
STOP
END
DCRSPR
0 0 0 1
END
DVENTR
001
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
1 0 0 0
1 1 1 1
003
7 1 2 2
004
10 10.00000
10 20.00000


8.03977E-01
2.24053E+01
2.18771E-02
1.43376E+01
4.88143E-03
1.14084E+01
6.99609E-03
2.02656E+01
3.44488E-02
3.28881E-09
2.06197E-01
7.31348E-05
1.69608E+01
5.78271E-03
6.40226E+01
1.47116E-01
9.03707E-05
1.60885E-01
7.07131E-05
0.OOOOOE+00
6.91678E+00
2.59628E+00
7.49866E+00
7.78330E+00
0.OOOOOE+00
2.70248E-02
1.16110E+01
4.83930E-05
3.88718E-01
0.OOOOOE+00
4.20050E-02
0.OOOOOE+00
1.24019E-02
2.39832E-06
1.89796E-01
3.58892E-05
8.19398E+00
1.91947E-04
7.28171E-05
3.87701E-02
4.11020E-05
4.88931E-01
4.30653E-04
2.34977E-01-
3.56776E-04


9.93761E-02
1.47284E+01
1.81619E-03
3.28635E+00
4.05247E-04
2.60307E+00
8.86252E-04
1.87737E+01
1.35167E-02
1.72807E-01
4.68691E-02
6.39782E-06
5.54775E+00
2.68446E-03
4.77361E+01
3.28849E-02
8.76571E-06
4.20387E-02
2.27381E-05
0.OOOOOE+00
2.11100E+00
9.42994E-02
3.99530E-01
5.45911E+00
0.OOOOOE+00
1.05520E-03
3.65611E+00
0.OOOOOE+00
1.05087E-01
0.OOOOOE+00
1.16205E-02
0.OOOOOE+00
4.25147E-03
0.OOOOOE+00
2.18851E-02
7.07541E-06
1.03770E+00
1.20724E-04
1.10486E+00
4.29353E-03
9.32957E-06
3.61459E-01
1.79215E-04
3.53042E-02-
7.67005E-05


8.13960E-03
4. 21559E+00
2.56319E-04
9.38527E-01
5.71927E-05
5.95004E-01
7.35750E-05
5.15716E+00
3.16307E-03
2.00673E+01
1.34159E-02
7.61115E-07
1.44961E+00
1.05368E-03
1.70310E+01
7.47482E-03
3.72931E+01
1.15307E-02
1.23857E-06
2.28256E+00
1.56074E-01
7.10944E-03
1.47341E-02
7.18006E-01
1.36791E+01
1.07724E-04
9.80184E-01
0.OOOOOE+00
1.42059E-02
1.89261E+01
1.88520E-03
1.46446E+01
1.36645E-03
3.57791E-02
3.73614E-03
1.94020E-06
1.58436E-01
5.38866E-05
2.12824E+01
8.29655E-04
1.25650E-06
4.32612E-02
8.78044E-05
-1.55596E-02
1.35015E-04


1.14874E-03
1.95653E+00
0.OOOOOE+00
4.29833E-01
0.OOOOOE+00
1.64880E-01
1.03837E-05
1.17513E+00
4.00693E-04
1.28708E+01
6.22796E-03
3.88012E-02
3.97611E-01
2.46988E-04
5.49705E+00
2.13960E-03
3.56796E+00
2.57746E-03
0.OOOOOE+00
1.37152E+00
0.OOOOOE+00
0.OOOOOE+00
1.16593E-03
3.84914E-02
1.42048E+01
0.OOOOOE+00
1.30264E-01
1.83671E+01
9.39060E-04
7.94556E+00
1.91677E-04
6.48811E+00
3.08703E-04
1.66481E+01
1.47909E-03
1.08592E-09
2.06729E-02
1.25409E-05
8.68491E+00
3.92353E-04
1.22197E+01
5.30875E-03-
3.38929E-05
5.57049E-03-
4.53985E-05


0.OOOOOE+00
7.64911E-01
0.OOOOOE+00
1.65173E-01
0.OOOOOE+00
7.61939E-02
0.OOOOOE+00
2.62381E-01
3.32647E-05
3.36310E+00
2.44453E-03
1.34070E+00
8.88781E-02
3.15218E-05
2.05267E+00
9.93252E-04
6.18797E-01
5.85864E-04
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
1.43535E-03
3.80015E+00
0.OOOOOE+00
7.16889E-03
8.41214E+00
7.67478E-05
8.91005E-01
2.71069E-05
7.30309E-01
4.86556E-05
1.13014E+01
5.82529E-04
1.78245E-01
2.51245E-03
2.77792E-06
2.07868E+00
1.93240E-04
2.32340E+01
2.11256E-04
4.32751E-06
1.24805E-04
1.56452E-05


0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0


0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0 0 0 0
1 0 1 0


0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0 0 0 0
0 0 2 1


0.OOOOOE+00
0.OOOOOE+00
0.OOOOOE+00
0 0 0 0
0 0 0 0


2 0 0 0 0 0 0 0 0

15 15.00000 5 10.00000 0
5 10.00000 5 10.00000 5 10.00000


3.20000E-11
5.00000E-06
0.OOOOOE+00
0 0 0 0
0 0 0 0


1.OOOOOE+00
5.00000E-05
0.OOOOOE+00
0 0 0 0
0 0 0 0


5 10.00000 5 10.00000













5 10.00000
005
6 6 6
1 1 6
2 2 6
3 3 6
4 4 6
5 5 6
7 7 6
7 7 6
7 7 6
012
0
1 1 1 1
2 2 2 2
3 3 3 3
4 4 4 4
5 5 5 5
6 6 6 6
7 7 7 7
0
013
2
1
IIX101
1
IIX102
1
IIX103
1
IIX104
1
IIX105
1
IIX612
2
IIX111IIX612
020
1 1
IIX101
2 2
IIX102
3 3
IIX103
4 4
IIX104
5 5
IIX105
6 6
IIX612 1.128:
7 7


5 10.00000 5 10.00000 0
















1.00000E+00
1.OOOOOE+00
1.OOOOOE+00
1.00000E+00
1.00000E+00
1.OOOOOE+00
1.OOOOOE+00

























1.0

1.0

1.0

1.0

1.0


18E-01


IIX111 1.92070E-03IIX612 7.89729E-02


END






















APPENDIX C
SAMPLE OF MCNP INPUT FILE


MCNP Input file for New Core Honeycomb core 006
c Cell Card


c hydrogen hole
1 1 0.0010807 -1
2 2 0.087594 1
c first fuel region
3 3 0.1425550 -101
4 3 0.1425550 -102 -
5 3 0.1425550 -103 -
6 3 0.1425550 -104 -
7 3 0.1425550 -105 -
8 3 0.1425550 -106 -
9 3 0.1425550 -107 -
10 3 0.1425550 -108 -
11 3 0.1425550 -109 -
12 3 0.1425550 -110 -
13 3 0.1425550 -111 -
14 3 0.1425550 -112 -
15 3 0.1425550 -113 -
16 3 0.1425550 -114 -
17 3 0.1425550 -115 -
18 3 0.1425550 -116 -
19 3 0.1425550 -117
20 3 0.1425550 -118
c zirconium hydrate
57 4 0.0432054 (2 -3


113 114 115
beryllium reflector
5 0.1236183 -12 11 -4
5 0.1236183 -11 13 3
everything outside
0 4:12:-13


-11 13 imp:n=l
-2 -11 13 imp:n=l


imp: n
imp: n=
imp: n
imp: n=
imp: n
imp: n=
imp: n
imp: n=
imp: n
imp: n=
imp: n
imp: n=
imp: n=
imp: n=
imp: n
imp: n
imp: n
imp: n


-11 13 101 102 103 104 105 106 107 108 109 110 111 112


116 117 118) imp:n=l


imp:n=1
imp:n=1

imp:n=0


c Surface Card
c Main Cylinder and center hole
1 cz 2.25
2 cz 2.5
3 cz 18.4
4 cz 28.4
c Axial Region of cylinder
11 pz 0.0
12 pz 10.0
13 pz -50.0
c First fuel region 6 fuel elements inside
101 c/z 7.3 0 3.5
102 c/z 3.65 -6.32 3.5
103 c/z -3.65 -6.32 3.5
104 c/z -7.3 0 3.5
105 c/z -3.65 6.32 3.5
106 c/z 3.65 6.32 3.5
c First fuel region 18 fuel elements outside












107 c/z 14.199 -3.805 3.5
108 c/z 10.394 -10.394 3.5
109 c/z 3.805 -14.199 3.5
110 c/z -3.805 -14.199 3.5
111 c/z -10.394 -10.394 3.5
112 c/z -14.199 -3.805 3.5
113 c/z -14.199 3.805 3.5
114 c/z -10.394 10.394 3.5
115 c/z -3.805 14.199 3.5
116 c/z 3.805 14.199 3.5
117 c/z 10.394 10.394 3.5
118 c/z 14.199 3.805 3.5

kcode 10000 1.0 5 100 2000
ksrc 0 0 -25 7.3 0 -25 -7.3 0 -25 3.65 -6.32 -25 -3.65 -6.32 -25
-3.65 6.32 -25 3.65 6.32 -25 14.199 -3.805 -25 10.394 -10.394 -25
3.805 -14.199 -25 -3.805 -14.199 -25 -10.394 -10.394 -25
-14.199 -3.805 -25 -14.199 3.805 -25 -10.394 10.394 -25
-3.805 14.199 -25 3.805 14.199 -25 10.394 10.394 -25 14.199 3.805 -25
c hydrogen hole
ml 1001.60c 1.0
c inconel tube
m2 24000.50c 0.17453 25055.60c 0.010324 26000.55c 0.10156
14000.60c 0.0089866 16000.60c 0.00026537 29000.50c 0.0039272
28000.50c 0.69569 6000.60c 0.0047221
c fuel and hydrogen graphite zirconium oxide
m3 92235 0.003671 92238 0.00027281 6000.60c 0.382048
40000.60c 0.340299 41093.60c 0.0177467 1001.60c 0.091254
8016.60c 0.164709
c zirconium hydrate
m4 40000.60c 1 1001.60c 2
c beryllium reflector
m5 4009.60c 1
mt4 zr/h.06 h/zr.06
mt5 be.06















REFERENCES


Borowski, S.K. and Clark, J.S. "Nuclear Thermal Propulsion Transportation System for
Lunar/Mars Exploration," Nuclear Power Engineering in Space Nuclear Rocket
Engines Conference, by Research and Production Association "LUCH," Lewis
Research Center, Cleveland, OH, September 1992.

Furman, E. "Thermal Hydraulic Design Analysis of Ternary Carbide Fueled Square-
Lattice Honeycomb Nuclear Rocket Engine," 16th Symposium on Space Nuclear
Power and Propulsion, edited by M.S. El-Genk, New York: AIP Conference
Proceedings, 1999.

Grimesey, R.A., Nigg, D.W., and Curtis, R.I. COMBINE/PC-A Portable ENDF/B
Version 5 Neutron Spectrum and Cross-Section Generation Program, Idaho Falls,
ID: EG&G Idaho, 1990.

Hendricks, J.S. MCNP4B, Monte Carlo N-Particle Tranport Code System Manual.
RSICC Computer Code Collection, Los Alamos, NM: Los Alamos National
Laboratories, 1997.

Horman, F.J., Napier, J.M., and Caldwell, C.S. "Particle Fuels Technology for Nuclear
Thermal Propulsion," AIAAJNASA/OAI Conference on Advanced SEI
Technologies, Cleveland, OH, September 1991.

Pelaccio, D.G. and El-Genk, M.S. "A Review of Nuclear Thermal Propulsion Carbide
Fuel Corrosion and Key Issues, Final Report", University of New Mexico,
Albuquerque, NM: November 1994.

Robbins, W. H. "An Historical Perspective of the NERVA Nuclear Rocket Engine
Technology Program," Lewis Research Center, Brook Park: OH, July 1991.

Shapiro, A., Huria, H.C., and Cho, K.W. VENTURE/PC Manual A Multidimensional
Multigroup Neutron Diffusion Code System Version 2, Idaho Falls, ID: EG&G
Idaho, 1990.















BIOGRAPHICAL SKETCH


Reza R. Gouw was born on March 3, 1972, under the name of Reza Widargo in

Malang, East Java, Indonesia. He lived in Indonesia for 18 years before his family

immigrated to the United States in 1991. In January 1998, he became a United States

citizen, and in March 1998, he changed his name to Reza Raymond Gouw.

He completed his elementary education at the Trinitas Elementary School in

Jakarta, Indonesia. He continued his education at the Karangturi High School in

Semarang, Central Java. When he was in 11th grade, his family moved to Melbourne,

Florida. He then finished his high school at the Florida Air Academy, graduating on May

31, 1992, with honors in physics and mathematic. He then enrolled in the University of

Florida, Gainesville, Florida, where he studied nuclear engineering. He received his

Bachelor of Science degree with honors in nuclear engineering from the University of

Florida in August 1997. In August 1997, he decided to continue his education by

enrolling in the Master of Engineering in Nuclear and Radiological Engineering program

at the University of Florida. He has worked for the Innovative Nuclear Space Power and

Propulsion Institute from 1997 to present. He is also a recipient of the U.S. Department

of Energy (DOE) Nuclear Engineering/Health Physics Fellowship. His responsibilities

and research interests are in the area of space nuclear power and propulsion.




University of Florida Home Page
© 2004 - 2010 University of Florida George A. Smathers Libraries.
All rights reserved.

Acceptable Use, Copyright, and Disclaimer Statement
Last updated October 10, 2010 - - mvs