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Properties of irradiated stainless steels for predicting lifetime of nuclear power plant components

Ziel

During operation components close to the core are subject to irradiation by neutrons, which induce changes in the properties of construction materials. For assessments of the structural integrity and remaining lifetime of these components, as well as for life extension purposes, relevant and valid data on t he material properties are required. At the present available data on these properties are very limited. This proposal aims at producing validated data on fracture resistance of irradiated austenitic stainless steels, and to investigate the properties of such materials as a function of neutron influence. Materials from both BWR and PWR internal components will be tested. As there are no established procedures for fracture toughness testing of miniature specimens, which is required in this case, validation of test procedures will be determined on unirradiated material prior to testing of irradiated material. The work proposed will significantly improve future assessments of the structural integrity of LWR internal components, and provide valuable information for plant life extension purposes.

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WESTINGHOUSE ATOM AB
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