last modified: 17-MAR-1982 | catalog | categories | new | search |

NEA-0538 SHOSPA-MOD.

SHOSPA-MOD, Hot Spot Factors for Fuel and Clad, Hot Channel Factors

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1. NAME OR DESIGNATION OF PROGRAM:  SHOSPA-MOD.
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2. COMPUTERS
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Program name Package id Status Status date
SHOSPA-MOD NEA-0538/01 Tested 17-MAR-1982

Machines used:

Package ID Orig. computer Test computer
NEA-0538/01 IBM 3033 IBM 3033
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3. NATURE OF PHYSICAL PROBLEM SOLVED

SHOSPA evaluates the hot spot factors for fuel and cladding as well as the hot channel factor as a function of the confidence level. Moreover, it evaluates the probability on n hot subassemblies. The code has been developed with emphasis on sodium cooled fast reactors, but it is applicable to any type of reactors constituted of bundled fuel rods with single phase  coolant. An option for  plotting is available in this version.
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4. METHODS: METHOD OF SOLUTION
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

This code is applicable to any type of reactors constituted of fuel rods with single phase coolant.
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6. TYPICAL RUNNING TIME:  NEADB executed the test case on IBM 3033 in 30 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM

In order to restrict the code to cosine axial power distribution, the FORTRAN functions FP and FC are not defined in the program, but they must be supplied by the user according to the actual axial profile as separate FUNCTION subroutines.
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-0538/01 17-MAR-1982 Tested at NEADB
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10. REFERENCES

- A.Amendola:
  'Advanced Statistical Hot Spot Analysis'
  Report KFK 1134, EUR 3678.E (March 1970).
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11. MACHINE REQUIREMENTS:  The test case requires 330 Kbytes on IBM 3033.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0538/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  OS370/033 VS2 03.8G (IBM 3033).
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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

     A. Amendola
     EURATOM
     Karlsruhe Fast Breeder Project,
     Institut fuer Reaktorentwicklung

     Joint Research Centre
     21020 - Ispra, Italy
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16. MATERIAL AVAILABLE
NEA-0538/01
File name File description Records
NEA0538_01.002 SHOSPA-MOD INFORMATION 65
NEA0538_01.003 ISOTEX1 SOURCE PROGRAM FORTRAN-4 2816
NEA0538_01.004 ISOTEX1 INPUT FOR TEST CASE 62
NEA0538_01.005 ISOTEX1 OUTPUT OF TEST CASE 2367
NEA0538_01.006 GRETEL SOURCE PROGRAM FORTRAN-4 1626
NEA0538_01.007 GRETEL INPUT FOR TEST CASE 43
NEA0538_01.008 GRETEL LIBRARY 3099
NEA0538_01.009 GRETEL OUTPUT OF TEST CASE 3287
NEA0538_01.010 SHOSPA-MOD SOURCE PROGRAM FORTRAN-4 776
NEA0538_01.011 SHOSPA-MOD INPUT FOR TEST CASE 224
NEA0538_01.012 SHOSPA-MOD OUTPUT OF TEST CASE 995
NEA0538_01.013 JCL TO EXEC ISOTEX1+GRETEL+SHOSPA-MOD 82
NEA0538_01.014 ISPOTEX1 OVERLAY CONTROL CARDS 4
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: fuel-cladding interaction, reactor safety, sodium cooled reactors.