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NEA-0995 IBIS.

IBIS, FBR 3-D Steady-State and Kinetics with Thermohydraulic Feedback

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1. NAME OR DESIGNATION OF PROGRAM:  IBIS: A three-dimensional nuclear
reactor kinetics calculation code.
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2. COMPUTERS
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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
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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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The number of neutron energy groups is fixed to 3 groups in the present version of the code.
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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).
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.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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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.
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9. STATUS
Package ID Status date Status
NEA-0995/01 28-JUL-1987 Tested at NEADB
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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.
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.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0995/01 FORTRAN-77
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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.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Mamoru Konomura, Nobuo Tada, Yoshiaki Oka and Shigehiro An
Nuclear Engineering Research Laboratory
Faculty of Engineering
University of Tokyo
Japan
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16. MATERIAL AVAILABLE
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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17. CATEGORIES
  • 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.