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NEA-1578 COMRAD96.

COMRAD96, Nuclear Fuel Burnup and Depletion Calculation System

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1. NAME OR DESIGNATION OF PROGRAM:  COMRAD96.
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2. COMPUTERS
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Program name Package id Status Status date
COMRAD96 NEA-1578/01 Tested 14-MAR-2002

Machines used:

Package ID Orig. computer Test computer
NEA-1578/01 SUN W.S. PC Pentium III,DEC ALPHA W.S.
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3. DESCRIPTION OF PROGRAM OR FUNCTION:  Burn-up calculation of nuclear fuel.
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4. METHODS:  Matrix exponential method, Bateman Equation.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

a) One-grouped cross section library should be prepared for the fuel system to be analyzed using UNITBURN. However, UNITBURN is not available now for UNIX systems.
b) Gamma ray spectrometry calculation will fail using the attached piflib  routine. This problem has already been rectified in the internal version.
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6. TYPICAL RUNNING TIME

Two minutes for standard burn-up calculation on Sun ULTRA 30.
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7. UNUSUAL FEATURES

a) Selection of Matrix exponential method, or Bateman Equation.
b) JDDL, a detailed decay chain data based on ENSDF.
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8. RELATED OR AUXILIARY PROGRAMS:  UNITBURN: Burnup calculation code unit cell system.
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9. STATUS
Package ID Status date Status
NEA-1578/01 14-MAR-2002 Tested at NEADB
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10. REFERENCES: REFERENCE:
NEA-1578/01, included references:
- K. Suyama et al.:
Burnup Calculation Code System COMRAD96
JAERI-Data/Code 97-021 (May 1997)
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11. HARDWARE REQUIREMENTS

HDD: 20 MByte, Memory: 64 MByte (including amount for OS or other system)
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1578/01 FORTRAN-77, C-LANGUAGE
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13. SOFTWARE REQUIREMENTS:  Sun OS 4.1.3 or later, Solaris 2.5.1 or later.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

COMRAD96  uses one-grouped cross section library prepared by UNITBURN. However, UNITBURN is not available on UNIX systems. This means that dependency of one-grouped cross sections on neutron spectrum cannot be treated.
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15. NAME AND ESTABLISHMENT OF AUTHORS

     K. Suyama
     Japan Atomic Energy Research Institute
     Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 JAPAN

     F. Masukawa
     Fuel Cycle Facility
     Safety Analysis Section
     NUPEC/Institute of Nuclear Safety
     17-1, 3-Chome Toranomon
     Minato-ku, TOKYO 105-0001

     M. Ido, M. Enomoto, S. Takyu, T. Hara
     Information Technologies Japan, Inc.
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16. MATERIAL AVAILABLE
NEA-1578/01
src/ALPH Source files (10 files)
src/CALC Source files (31 files)
src/GAM1 Source files (9 files)
src/GAM2 Source files (35 files)
src/LIB Source file library (31 files)
src/SF Source files (7 files)
src/common Source files (9 files)
src/Makefile Makefile
src/pif-v2.61 Graphics files (42 files)
src/PRECOMRAD Source files (20 files)
src/INFSIGMA Source files (5 files)
src/ggsx-1.1 Source files (126 files)
lib Data library
bin Bin file
sample/libmaint Sample data (37 files)
sample/alph Sample data (4 files)
sample/gam Sample data (7 files)
sample/comrad Sample data (7 files)
sample/infsigma Sample data (7 files)
sample/jddl1gxs Sample data (5 files)
sample/precomrad Sample data (9 files)
sample/unitburn Sample data UNITBURN (4 files)
sample/Run_Sample
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, depletion.