Computer Programs
NEA-0558 BUST.
last modified: 07-NOV-1984 | catalog | categories | new | search |

NEA-0558 BUST.

BUST, Elastic Stress in HTGR Pressurized Fuel Elements

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1. NAME OR DESIGNATION OF PROGRAM:  BUST.
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2. COMPUTERS
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Program name Package id Status Status date
BUST NEA-0558/02 Tested 07-NOV-1984

Machines used:

Package ID Orig. computer Test computer
NEA-0558/02 IBM 370 series IBM 3081
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3. NATURE OF PHYSICAL PROBLEM SOLVED

Calculation of elastic stresses in block type elements when the fuel holes are pressurised.
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4. METHOD OF SOLUTION:  The finite element method.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME
NEA-0558/02
NEA-DB executed the test case on IBM 3081 in 7 seconds  of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

This programme was written as part of an experiment to test fuel for the Dragon High Temperature Reactor.
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8. RELATED AND AUXILIARY PROGRAMS:  STABA, STIG.
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9. STATUS
Package ID Status date Status
NEA-0558/02 07-NOV-1984 Tested at NEADB
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10. REFERENCES
NEA-0558/02, included references:
- B.E. Pitchford:
  'BUST'
  Dragon Project Technical Note DPTN/807 (May 1976).
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11. MACHINE REQUIREMENTS:  288K bytes of main storage on IBM 3081.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0558/02 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBM 370 OS.
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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.E.Pitchford
           OECD High Temperature Reactor Project
           AEE Winfrith, Dorchester Dorset, England
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16. MATERIAL AVAILABLE
NEA-0558/02
File name File description Records
NEA0558_02.003 BUST INFORMATION FILE 66
NEA0558_02.004 BUST SOURCE (CARD IMAGES) 409
NEA0558_02.005 JCL 47
NEA0558_02.006 BUST TEST CASE INPUT DATA 492
NEA0558_02.007 BUST TEST CASE PRINTED OUTPUT 952
NEA0558_02.008 BUST TEST CASE PUNCHED OUTPUT 162
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17. CATEGORIES
  • I. Deformation and Stress Distributions, Structural Analysis and Engineering Design Studies

Keywords: HTR reactors, elasticity, finite element method, fuel elements, graphite moderated reactors, stresses.