Abstract
Pressurized thermal shock experiments are performed in the Prometey Institute for the purpose of investigating the behaviour of surface flaws under pressurized water reactor overcooling accident conditions. The model pressure vessels are made of a steel 15X2MFA. The specific aim of the tests is to determine whether a surface flaw would be critical during a very severe pressurized thermal shock loading, and how well this situation can be predicted. In the tests with the second vessel the effect of the cladding on the fracture behaviour is studied. The preliminary finite-element analyses for the tests with the first model vessel and the pre-test analyses for the test with the second model vessel were presented in this paper.
Original language | English |
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Title of host publication | 18. MPA seminar on safety and reliability of plant technology |
Subtitle of host publication | Safety aspects for long operational life and new reactor concepts |
Place of Publication | Stuttgart |
Pages | 15.1-15.24 |
Publication status | Published - 1992 |
MoE publication type | B3 Non-refereed article in conference proceedings |
Event | 18th MPA-seminar Safety and Reliability of Plant Technology - Stuttgart, Germany Duration: 8 Oct 1992 → 9 Oct 1992 |
Seminar
Seminar | 18th MPA-seminar Safety and Reliability of Plant Technology |
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Country/Territory | Germany |
City | Stuttgart |
Period | 8/10/92 → 9/10/92 |