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)
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)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36034266
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAILURES; FRACTURE MECHANICS; LEAKS; NONDESTRUCTIVE TESTING; PRIMARY COOLANT CIRCUITS; PROBABILISTIC ESTIMATION; PROCESS HEAT; PWR TYPE REACTORS; RISK ASSESSMENT; STEAM GENERATION; STOCHASTIC PROCESSES
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; ENERGY; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT; MATERIALS TESTING; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs, 4 figs