last modified: 01-FEB-1974 | catalog | categories | new | search |

NEA-0407 SCORE-4.

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

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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.