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

• Research unit: EU RFP
• Project number: 99.0715

Key words (English)

Environmentally-assisted cracking; low-alloy steel; light water reactor; crack growth rate; primary pressure boundary components; transient operation conditions;
Nuclear Fission; Radiation Protection; Safety

Alternative project number (English)

EU project number: FIKS-2000-00048

Research programs (English)

EU-programme: 5. Frame Research Programme - 5.5.2 Nuclear fission

Short description (English)

See abstract

Further information (English)

Full name of research-institution/enterprise:
Paul Scherrer Institut PSI
Laboratory for Safety and Accident Research

Partners and International Organizations (English)

Coordinator: MPA Stuttgart (D)

Abstract (English)

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.

References in databases (English)

Swiss Database: Euro-DB of the
State Secretariat for Education and Research
Hallwylstrasse 4
CH-3003 Berne, Switzerland
Tel. [phone]
Swiss Project-Number: 99.0715