last modified: 18-OCT-1983 | catalog | categories | new | search |

NEA-0556 TAPIR.

TAPIR, Thermal Analysis of HTGR with Graphite Sleeve Fuel Elements

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1. NAME OR DESIGNATION OF PROGRAM:  TAPIR.
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2. COMPUTERS
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Program name Package id Status Status date
TAPIR NEA-0556/02 Tested 18-OCT-1983

Machines used:

Package ID Orig. computer Test computer
NEA-0556/02 IBM 3081 IBM 3081
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3. NATURE OF PHYSICAL PROBLEM SOLVED

Thermal analysis of a reactor core containing internally and/or externally gas cooled prismatic fuel elements of various geometries, rating, power distribution, and material properties.
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4. METHOD OF SOLUTION

A fuel element in this programme is regarded as a sector of a fuelled annulus with graphite sleeves of any shape on  either side and optional annular gaps between fuel and graphite and/or within the graphite. It may have any centre angle and the fuelled annulus may become a solid cylindrical rod. Heat generation  in the fuel is assumed to be uniform over the cross section and peripheral heat flux into adjacent sectors is ignored.
Fuel elements and coolant channels are treated separately, then linked together to fit a specified pattern.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maxima of -    50 fuel elements
               50 cooled channels
               25 fuel geometries
               25 coolant channel geometries
               10 axial power distributions
               10 graphite conductivities.
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6. TYPICAL RUNNING TIME

NEA-DB executed the test case included in the  package (NEA 0556/01) on IBM 3081 in one second of CPU time.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS:  COCKTAIL
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9. STATUS
Package ID Status date Status
NEA-0556/02 18-OCT-1983 Tested at NEADB
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10. REFERENCES

- U. Weicht, W. Mueller:
  'TAPIR - COCO - DELTAP',Three Programmes for the Thermal Analysis of A Reactor Core Containing Internally and/or Externally Gas Cooled Prismatic Fuel Elements.
  Dragon Project Report 748.
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11. MACHINE REQUIREMENTS:  Main storage requirements on IBM 3081 are 140K bytes.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0556/02 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  MVS-SP (IBM 3081).
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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

      U. Weicht and W. Mueller
      OECD High Temperature Project Dragon,
      AEE Winfrith,Dorchester,Dorset,England
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16. MATERIAL AVAILABLE
NEA-0556/02
File name File description Records
NEA0556_02.003 TAPIR INFORMATION FILE 54
NEA0556_02.004 TAPIR SOURCE (FORTRAN-4) 840
NEA0556_02.005 TAPIR INPUT DATA FOR TEST CASE 87
NEA0556_02.006 TAPIR OUTPUT OF TEST CASE 294
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17. CATEGORIES
  • H. Heat Transfer and Fluid Flow

Keywords: fuel elements, graphite moderated reactors, reactor cores, thermal analysis.