last modified: 07-NOV-1984 | catalog | categories | new | search |

NEA-0558 BUST.

BUST, Elastic Stress in HTGR Pressurized Fuel Elements

top ]
1. NAME OR DESIGNATION OF PROGRAM:  BUST.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
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
top ]
3. NATURE OF PHYSICAL PROBLEM SOLVED

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

This programme was written as part of an experiment to test fuel for the Dragon High Temperature Reactor.
top ]
8. RELATED AND AUXILIARY PROGRAMS:  STABA, STIG.
top ]
9. STATUS
Package ID Status date Status
NEA-0558/02 07-NOV-1984 Tested at NEADB
top ]
10. REFERENCES
NEA-0558/02, included references:
- B.E. Pitchford:
  'BUST'
  Dragon Project Technical Note DPTN/807 (May 1976).
top ]
11. MACHINE REQUIREMENTS:  288K bytes of main storage on IBM 3081.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0558/02 FORTRAN-IV
top ]
13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBM 370 OS.
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

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

           B.E.Pitchford
           OECD High Temperature Reactor Project
           AEE Winfrith, Dorchester Dorset, England
top ]
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
top ]
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.