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NEA-0407 SCORE-4.

SCORE-4, 2-D Removal Diffusion in X-Y or R-Z Geometry for Rectangular Shields

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, FEATURES, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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1. NAME OR DESIGNATION OF PROGRAM:  SCORE-4.
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2. COMPUTERS
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Program name Package id Status Status date
SCORE-4 NEA-0407/01 Tested 01-FEB-1974

Machines used:

Package ID Orig. computer Test computer
NEA-0407/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The neutron flux is calculated for a shield made up of rectangular regions. The geometry is either  x-y or r-z.
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4. METHOD OF SOLUTION

Removal fluxes and sources throughout the shield regions are calculated from a given reactor core power distribution  using a point kernel method. The diffusion neutron fluxes are obtained from the removal source distribution using an iterative method of solution.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The amount of fast core required for the program depends on the size of shield being calculated. For example, a 100 by 100 mesh shielding calculation would require approximately 300k bytes. Larger problems could be solved by increasing the fast storage requirements.
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6. TYPICAL RUNNING TIME

Variable 2 hours IBM 370/165 time for a whole  shield calculation.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS:  SCORE-70, SCORE-M.
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9. STATUS
Package ID Status date Status
NEA-0407/01 01-FEB-1974 Tested at NEADB
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10. REFERENCES

- B. L. Richardson:
  'SCORE, A User's Guide'
  RPC/SN/P(71)2.
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0407/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBM 370/OS, RIOS.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

    B.L. Richardson
    CTS, UKAEA Reactor Group
    Risley, United Kingdom.
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16. MATERIAL AVAILABLE
NEA-0407/01
File name File description Records
NEA0407_01.001 CROSS SECTION DATA LIBRARY (BCD) 4779
NEA0407_01.002 BINARY TAPE MAKER 27
NEA0407_01.003 SCORE-3 SOURCE PROGRAM (FORTRAN) 4561
NEA0407_01.004 LIBRARY SUBROUTINES (FORTRAN+ASSEMBLER) 549
NEA0407_01.005 DATA SET DEFINITION CARDS 10
NEA0407_01.006 SAMPLE PROBLEMS (2 CASES) 196
NEA0407_01.007 OUTPUT LIST OF SAMPLE PROBLEM CASE 1 1358
NEA0407_01.008 OUTPUT LIST OF SAMPLE PROBLEM CASE 2 5771
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: diffusion, iterative methods, neutron flux, point kernels, r-z, shielding, x-y.