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NEA-1081 SLAROM.

SLAROM, Neutron Flux Distribution and Spectra in Lattice Cell

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1. NAME OR DESIGNATION OF PROGRAM:  SLAROM.
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2. COMPUTERS
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Program name Package id Status Status date
SLAROM NEA-1081/01 Arrived 04-FEB-2002

Machines used:

Package ID Orig. computer Test computer
NEA-1081/01 FACOM M-380
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3. DESCRIPTION OF PROGRAM OR FUNCTION

SLAROM solves the neutron integral transport equations to determine flux distribution and spectra in a lattice and calculates cell averaged effective cross sections.
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4. METHOD OF SOLUTION

Collision probability method for cell calculation and 1D diffusion for core calculation.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Variable dimensions  are used throughout the program so that computer core requirements depend on a variety of program parameters.
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6. TYPICAL RUNNING TIME

It varies with geometry option and number of  spatial regions. An infinite plate geometry problem with 14 regions  requires about 30 sec CPU on a FACOM M-380.
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7. UNUSUAL FEATURES OF THE PROGRAM

PDS files are used to keep the macroscopic and microscopic cross sections, etc.
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8. RELATED AND AUXILIARY PROGRAMS

Cross section library of JFS2 or JFS3 type which may be generated by the TISM-PGG code. The MIX code  to compose macroscopic cross sections and the PDSDMP code to print out data saved in a PDS file.
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9. STATUS
Package ID Status date Status
NEA-1081/01 04-FEB-2002 Masterfiled Arrived
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10. REFERENCES:
NEA-1081/01, included references:
- M. Nakagawa and K. Tsuchihashi:
  A Code for Cell Homogenization Calculation of Fast Reactor.
  JAERI-1294  (December 1984)
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11. MACHINE REQUIREMENTS

Core requirements depend on problem complexity but virtually any reasonable problem may be executed in 1 M bytes of core storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1081/01 FORTRAN+ASSEMBLER
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  FACOM OS IV.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

A PDS (Partioned Data Set) file is used with undefined record format.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          M. Nakagawa and K. Tsuchihashi
          Department of Reactor Engineering
          Tokai Research Establishment, JAERI
          Tokai-mura, Naka-gun, Ibaraki-Ken, 319-11, Japan
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16. MATERIAL AVAILABLE
NEA-1081/01
source program   mag tapeLibrary Converter Source (Fortran-IV)      SRCTP
symb data lib    mag tapeData Library (BCD Form)                    LBSTP
test-case output mag tapeLibrary Output                             OUTTP
source program   mag tapeSLAROM Source Program (Fortran-IV)         SRCTP
bin data lib     mag tapeData Library (Binary)                      LBBTP
test-case data   mag tapeOverlay Card                               DATTP
test-case data   mag tapeJCL                                        DATTP
test-case data   mag tapeSample Input Case 1                        DATTP
test-case data   mag tapeSample Input Case 2                        DATTP
test-case output mag tapeSample Output Case 1                       OUTTP
test-case output mag tapeSample Output Case 2                       OUTTP
source program   mag tapeLibrary Converter Source (Fortran-IV)      SRCTP
symb data lib    mag tapeData Library (BCD Form)                    LBSTP
test-case output mag tapeLibrary Output                             OUTTP
source program   mag tapeSLAROM Source Program (Fortran-IV)         SRCTP
bin data lib     mag tapeData Library (Binary)                      LBBTP
test-case data   mag tapeOverlay Card                               DATTP
test-case data   mag tapeJCL                                        DATTP
test-case data   mag tapeSample Input Case 1                        DATTP
test-case data   mag tapeSample Input Case 2                        DATTP
test-case output mag tapeSample Output Case 1                       OUTTP
test-case output mag tapeSample Output Case 2                       OUTTP
report                   JAERI 1294  (December 1984)                REPPT
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17. CATEGORIES
  • C. Static Design Studies

Keywords: cell calculation, neutron flux, neutron spectra, transport.