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

Objective

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.

Funding Scheme

CSC - Cost-sharing contracts

Coordinator

WESTINGHOUSE ATOM AB
Address
Gideonsbergsgatan 2
721 63 Vaesteraas
Sweden

Participants (6)

BELGIAN NUCLEAR RESEARCH CENTRE
Belgium
Address
200,Boeretang 200
2400 Mol
CENTRO DE INVESTIGACIONES ENERGETICAS, MEDIAMBIENTALES Y TECNOLOGICAS
Spain
Address
Avenida Complutense 22
Madrid
FRAMATOME ANP GMBH
Germany
Address
Freyeslebenstrasse 1
91058 Erlangen
SOCIETE FRAMATOME
France
Address
1,Tour Framatome
92084 Paris La Defense
STUDSVIK NUCLEAR AB
Sweden
Address

611 82 Nykoping
TECHNICAL RESEARCH CENTRE OF FINLAND
Finland
Address
3,Kemistintie 3
02044 Espoo