NEA-0995 IBIS.
IBIS, FBR 3-D Steady-State and Kinetics with Thermohydraulic Feedback
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IBIS | NEA-0995/01 | Tested | 28-JUL-1987 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0995/01 | HITAC M-200 H | IBM 3084 |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
The IBIS code performs steady state and kinetics calculations based on a three-dimensional nuclear diffusion kinetics with thermal hydraulic feedback.
It can calculate the following values in hexagonal-Z geometry of a fast breeder reactor core through the progress of transient
(1) Net reactivity
(2) Total and groupwise delayed neutron fraction
(3) Groupwise delayed neutron precursor concentration
(4) Total power and energy
(5) Space dependent neutron flux in each energy group
(6) Space dependent temperature of each material
(7) Maximum temperature of each material and its location
The IBIS code performs steady state and kinetics calculations based on a three-dimensional nuclear diffusion kinetics with thermal hydraulic feedback.
It can calculate the following values in hexagonal-Z geometry of a fast breeder reactor core through the progress of transient
(1) Net reactivity
(2) Total and groupwise delayed neutron fraction
(3) Groupwise delayed neutron precursor concentration
(4) Total power and energy
(5) Space dependent neutron flux in each energy group
(6) Space dependent temperature of each material
(7) Maximum temperature of each material and its location
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4. METHOD OF SOLUTION
The quasi-static method is adopted to solve the three-dimensional nuclear diffusion kinetics problem. The method is the same as employed in the code QX1. The shape function equation is solved with the finite difference treatment as used in the codes CITATION and HONEYCOMB.
One-dimensional thermo-hydraulics is solved with a model similar to that given in the code SASLA. Sodium boiling can be taken into account.
The quasi-static method is adopted to solve the three-dimensional nuclear diffusion kinetics problem. The method is the same as employed in the code QX1. The shape function equation is solved with the finite difference treatment as used in the codes CITATION and HONEYCOMB.
One-dimensional thermo-hydraulics is solved with a model similar to that given in the code SASLA. Sodium boiling can be taken into account.
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6. TYPICAL RUNNING TIME
The sample problem included in the code package required about 15 minutes CPU time for the steady state calculation and about 34 minutes for the 1-sec transient calculation on HITAC M-200H with integrated array processor (IAP).
The sample problem included in the code package required about 15 minutes CPU time for the steady state calculation and about 34 minutes for the 1-sec transient calculation on HITAC M-200H with integrated array processor (IAP).
NEA-0995/01
Since the execution of the test case included in this package draws heavily on computer resources (6500K bytes of main storage and ca. 60 minutes of CPU time), the program has only been compiled at NEA-DB.[ top ]
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8. RELATED AND AUXILIARY PROGRAMS
PAINTV: an output processing routine for drawing contour maps of neutron flux or material temperature in an arbitrary horizontal or vertical section.
INFORMATIONS: In this version of IBIS, only the JAERI fast 25 group neutron cross section set can be read. It is collapsed to 3 groups and used for calculation.
PAINTV: an output processing routine for drawing contour maps of neutron flux or material temperature in an arbitrary horizontal or vertical section.
INFORMATIONS: In this version of IBIS, only the JAERI fast 25 group neutron cross section set can be read. It is collapsed to 3 groups and used for calculation.
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10. REFERENCES
- A. Hasegawa, et al.,
"JAERI-fast 70 Group Structure Constants Utility Programme System: J-FAST-70U",
JAERI-M-5381, (1973).
- D.A. Meneley, et al.,
"Fast-Reactor Kinetics - The QX1 Code",
ANL-7769, (1971).
- T.B. Fowler, et al.,
"Nuclear Reactor Code Analysis Code: CITATION",
ORNL-TM-2496, Rev. 2, (1969).
- T. Suzuki,
"Development Study on Computer Program HONEYCOMB for Analyzing
Detailed Nuclear Characteristics of Fast Breeder Reactor Core",
JAERI-M-6677 (in Japanese), (1976).
- J.C. Carter, et al.,
"SASLA, A Computer Code for the Analysis of Fast-Reactor Power and Flow Transients",
ANL-7607, (1970).
- McArthur, G.R. ed.,
"An Introduction to the SCD Graphics System",
NCAR-TN/161+1A, (1981).
- "The System Plot Package",
NCAR-TN/162+1A, (19810.
- "The SCD Graphics Utilities",
NCAR-TN/166+1A, (1981).
- M. Konomura et al.,
"Development of Three Dimensional Space Dependent Kinetics Code,
IBIS and Analysis of Transient Behavior of Homogeneous and
Hetergeneous LMFBR Cores"
Sumitted to J. Nucl. Sci. Technol.
- A. Hasegawa, et al.,
"JAERI-fast 70 Group Structure Constants Utility Programme System: J-FAST-70U",
JAERI-M-5381, (1973).
- D.A. Meneley, et al.,
"Fast-Reactor Kinetics - The QX1 Code",
ANL-7769, (1971).
- T.B. Fowler, et al.,
"Nuclear Reactor Code Analysis Code: CITATION",
ORNL-TM-2496, Rev. 2, (1969).
- T. Suzuki,
"Development Study on Computer Program HONEYCOMB for Analyzing
Detailed Nuclear Characteristics of Fast Breeder Reactor Core",
JAERI-M-6677 (in Japanese), (1976).
- J.C. Carter, et al.,
"SASLA, A Computer Code for the Analysis of Fast-Reactor Power and Flow Transients",
ANL-7607, (1970).
- McArthur, G.R. ed.,
"An Introduction to the SCD Graphics System",
NCAR-TN/161+1A, (1981).
- "The System Plot Package",
NCAR-TN/162+1A, (19810.
- "The SCD Graphics Utilities",
NCAR-TN/166+1A, (1981).
- M. Konomura et al.,
"Development of Three Dimensional Space Dependent Kinetics Code,
IBIS and Analysis of Transient Behavior of Homogeneous and
Hetergeneous LMFBR Cores"
Sumitted to J. Nucl. Sci. Technol.
NEA-0995/01, included references:
- A 3D Nuclear Reactor Kinetics Calculational Code.- M. Konomura, Y. Oka and S. An:
IBIS: Three-Dimensional Nuclear Reactor Kinetics Code. (Version 1)
UTNL-R 0153 (March 1983)
- N. Tada, Y. Oka, M. Konomura, S. Kondo and S. An:
Three-Dimensional Kinetics Analysis of Large LMFBR Cores with
Thermal Hydraulic Feedback.
UTNL-R 0166 (September 3, 1984)
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11. MACHINE REQUIREMENTS
IBIS has been implemented on the HITAC M-200H computer at the computer centre, University of Tokyo. The core requirement for the calculation of the sample problem in which the number of diagonal sub-assemblies of the core hexagon is 33, is 6500KB. Maximum number of auxiliary storage devices, in addition to the standard input output devices, is 29 and minimum space allocation on them is 21000KB.
IBIS has been implemented on the HITAC M-200H computer at the computer centre, University of Tokyo. The core requirement for the calculation of the sample problem in which the number of diagonal sub-assemblies of the core hexagon is 33, is 6500KB. Maximum number of auxiliary storage devices, in addition to the standard input output devices, is 29 and minimum space allocation on them is 21000KB.
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED
The IBIS code is written in FORTRAN 77 (fixed style). For other systems, The subroutine CLOCK which is called to sample CPU time, should be replaced by an appropriate subroutine.
The auxiliary routine PAINTV is written in FORTRAN 77 (free style). It utilizes some subroutines of the SCD graphics system offered by the National Center for Atomospheric Research, USA.
The IBIS code is written in FORTRAN 77 (fixed style). For other systems, The subroutine CLOCK which is called to sample CPU time, should be replaced by an appropriate subroutine.
The auxiliary routine PAINTV is written in FORTRAN 77 (free style). It utilizes some subroutines of the SCD graphics system offered by the National Center for Atomospheric Research, USA.
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NEA-0995/01
| File name | File description | Records |
|---|---|---|
| NEA0995_01.001 | Information file | 61 |
| NEA0995_01.002 | IBIS Fortran source | 7492 |
| NEA0995_01.003 | IBIS JCL | 11 |
| NEA0995_01.004 | IBIS sample input data | 327 |
| NEA0995_01.005 | IBIS restart run | 5 |
| NEA0995_01.006 | IBIS sample output | 1317 |
| NEA0995_01.007 | PAINTV source program | 365 |
| NEA0995_01.008 | PAINTV JCL | 13 |
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- F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
Keywords: diffusion equations, fast breeder reactors, feedback, hydraulics, kinetics, reactor kinetics, steady-state conditions, thermodynamics, three-dimensional.