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Crack growth behaviour of low alloy steel for pressure boundary components under transient light water reactor (LWR) operating conditions

Objective

The proposal addresses the ageing of primary pressure boundary components of nuclear power plants by environmentally assisted cracking. In particular, it deals with the crack growth behaviour of low alloy steels for reactor pressure vessels (eastern and western type) in light water reactor environment under static and cyclic load. Besides different crack geometries and specimen sizes transient conditions as postulated for plant operation will be considered during the test by varying water chemistry and mechanical load. The initiation of environmentally assisted cracking in pre-fatigued specimens will be forced by cyclic loading in the test environment. The results will lead to recommendations for service operation and for Code implementations. They will broaden the database for the lifetime assessment of nuclear power plants.

Funding Scheme

CSC - Cost-sharing contracts

Coordinator

UNIVERSITAET STUTTGART
Address
Pfaffenwaldring 32
70569 Stuttgart
Germany

Participants (5)

CENTRO DE INVESTIGACIONES ENERGETICAS, MEDIAMBIENTALES Y TECNOLOGICAS
Spain
Address
Avenida Complutense 22
Madrid
FRAMATOME ANP GMBH
Germany
Address
Freyeslebenstrasse 1
91058 Erlangen
NUCLEAR RESEARCH INSTITUTE REZ A.S.
Czechia
Address
Rez 130
250 68 Rez - Praha
PAUL SCHERRER INSTITUT
Switzerland
Address

5232 Villigen
TECHNICAL RESEARCH CENTRE OF FINLAND
Finland
Address
3,Kemistintie 3
02044 Espoo