Descriptive characteristics of different types of test for irradiation embrittlement

Within the IAEA coordinated programme on optimizing of reactor pressure vessel surveillance programmes and their analysis, phase 3, a specially tailored radiation sensitive correlation monitor material, a Japanese steel plate with code designation JRQ, a French forging material (FFA) and a Japanese...

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Bibliographic Details
Published in:Nuclear engineering and design 1995-10, Vol.159 (1), p.69-80
Main Authors: Wallin, Kim, Valo, Matti, Rintamaa, Rauno, Törrönen, Kari, Ahlstrand, Ralf
Format: Article
Language:English
Subjects:
Applied sciences
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Installations for energy generation and conversion: thermal and electrical energy
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Summary:Within the IAEA coordinated programme on optimizing of reactor pressure vessel surveillance programmes and their analysis, phase 3, a specially tailored radiation sensitive correlation monitor material, a Japanese steel plate with code designation JRQ, a French forging material (FFA) and a Japanese forging material (JFL) were selected for the investigations to be carried out in Finland. Based on the evaluation of the experimental results it was demonstrated that dynamic fracture toughness transition shift is equivalent to the Charpy-V shift, but the static fracture toughness transition shift may be considerably larger than the dyanamic shift. Thus, Charpy-V is not suitable for estimating the static fracture toughness transition shift. These findings have a strong impact upon the design of future surveillance programmes.
ISSN:0029-5493
1872-759X
DOI:10.1016/0029-5493(95)01054-L