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.

Fields of science

• natural sciences › computer and information sciences › databases
• engineering and technology › other engineering and technologies › nuclear engineering
• natural sciences › mathematics › pure mathematics › geometry

Programme(s)

• FP5-EAECTP C - Research and training programme (Euratom) in the field of nuclear energy (1998 to 2002)

Topic(s)

• 2.1.2.-1.1.1 - Integrity of equipment and structures

Call for proposal

Data not available

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