Published 1993 | Version v1
Book

Sensitivity of and influences on the reliability of an HTR-module primary circuit pressure boundary

Creators

  • 1. Research Centre Juelich GmbH (KFA), Institute for Safety Research and Reactor Technology, Juelich (Germany)

Description

The reliability of HTR-Modules for process-heat application and for electricity and steam generation was analysed for normal operation and under accident conditions. The probabilistic fracture mechanics assessment was performed with FORM/SORM on the basis of the widely used data. The calculated failure probabilities may thus be compared with similar investigations. The HTR-Module primary circuit pressure boundary as a unit showed leak-before-break behaviour in a probabilistic sense although not all of its parts did so. However, the findings may strongly depend on the stochastic data. Therefore a stochastic reference problem is defined and the results are compared to the Japanese Round Robin on a PWR section /6/. Possible changes of failure probabilities and of the leak-before-break behaviour are discussed for different criteria for the occurrence of a leak and for deviations from the stochastic reference problem such as the inclusion of NDE. The results may be used to identify those stochastic variables which have the greatest influence on the computed failure probabilities and to perhaps justify further work to provide more detailed information on them. (author)

Part of:
Transactions of the 12. international conference on Structural Mechanics in Reactor Technology (SMiRT). Volume M: Structural reliability and Probabilistic Safety Assessment (PSA). Volume N: Decommissioning, waste management and related technologies

Additional details

Publishing Information

Publisher
Elsevier
Imprint Place
Amsterdam (Netherlands)
ISBN
0-444-81515-5
Imprint Title
Transactions of the 12. international conference on Structural Mechanics in Reactor Technology (SMiRT). Volume M: Structural reliability and Probabilistic Safety Assessment (PSA). Volume N: Decommissioning, waste management and related technologies
Imprint Pagination
382 p.
Journal Page Range
p. 147-152

Conference

Title
12. international conference on Structural Mechanics in Reactor Technology
Acronym
SMiRT 12
Dates
15-20 Aug 1993
Place
Stuttgart (Germany)

Optional Information

Notes
8 refs, 4 figs