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IAEA0935 REX2-87.

REX1-87, MultiGroup Neutron Cross-Sections from ENDF/B

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1. NAME OR DESIGNATION OF PROGRAM:  REX2-87.
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2. COMPUTERS
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Program name Package id Status Status date
REX2-87 IAEA0935/02 Tested 08-NOV-1988

Machines used:

Package ID Orig. computer Test computer
IAEA0935/02 HONEYWELL DPS-8 DEC VAX 8810
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The program calculates self- shielding factors for reactor applications from a preprocessed (linearised) evaluated nuclear data file in the ENDF/B format.
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4. METHOD OF SOLUTION

Bondarenko definition of multigroup self- shielding factors invoking narrow resonance treatment is used.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

a) Maximum no. of energy group is 620.
b) Only the builtin forms of the weighting functions can be chosen.
c) The program is strictly limited to resolved resonance region from    physical considerations.
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6. TYPICAL RUNNING TIME

Less than five minutes for a typical problem  given as sample.
IAEA0935/02
The two test cases included in this package were executed by NEA-DB on a VAX 8810 computer in 85 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

a) Simple Input.
b) Any number of energy points can be handled.
c) Most suitable for fast reactor applications.
d) Default options, for group structure, weighting functions etc.    are built in.
e) Double precision treatment.
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8. RELATED AND AUXILIARY PROGRAMS

a) Supersedes earlier versions.
b) This program is usually used after preprocessing the evaluated    data by programs LINEAR , RECENT and SIGMA1 of D.E. Cullen.
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9. STATUS
Package ID Status date Status
IAEA0935/02 08-NOV-1988 Tested at NEADB
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10. REFERENCES:
IAEA0935/02, included references:
- V. Gopalakrishnan and S. Ganesan:
  REX2-87 - A Code for Calculating Self-Shielded Multigroup
  Neutron Cross Sections AND Self-Shielding Factors from
  Preprocessed ENDF/B Basic Data File.
  IGCAR/NDS-18  (August 1988)
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11. MACHINE REQUIREMENTS

a) Main memory around 60K.
b) Requires one scratch units on a direct access device (Disk Pack),    and usual I/O units.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0935/02 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  Any operating system supporting FORTRAN-IV.
IAEA0935/02
VAX VMS V5.0-1 with VAX FORTRAN V5.0-1 compiler.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Simple
FORTRAN-IV statements are used. Special features like, CHARACTER, NAMELIST, etc. are purposely avoided so that the program may be transportable. Slight changes (e.g. a special character prefixed to  the statement numbers corresponding to multiple returns) may be required to implement in a different system.
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15. NAME AND ESTABLISHMENT OF AUTHORS

               V. Gopalakrishnan and S. Ganesan
               Nuclear Data Section
               Indira Ghandi Centre for Atomic Research
               KALPAKKAM 603 102
               TAMIL NADU, India
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16. MATERIAL AVAILABLE
IAEA0935/02
File name File description Records
IAEA0935_02.001 Information file 83
IAEA0935_02.002 FORTRAN-IV source 1325
IAEA0935_02.003 Sample case 1/Data 1 to be fed from FT05 5
IAEA0935_02.004 Sample case 1/Data 2 to be fed from FT03 23704
IAEA0935_02.005 Output of sample case 1/ written on FT06 126
IAEA0935_02.006 Output of sample case 1/ written on FT02 20
IAEA0935_02.007 Sample case 2/Data 1 to be fed from FT05 4
IAEA0935_02.008 Sample case 2/Data 1 to be fed from FT03 7054
IAEA0935_02.009 Output of sample case 2/written on FT06 279
IAEA0935_02.010 Output of sample case 2/written on FT02 120
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems

Keywords: Doppler broadening, ENDF/B, data processing, evaluated data, group constants, interpolation, multigroup, neutron cross sections, self-shielding.