Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results

Margolin, B. Z. / Kursevich, I. P. / Sorokin, A. A. et al. | British Library Online Contents | 2009

Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 2. Relation between irradiation swelling and irradiation embrittlement. Physical and mechanical behavior

Margolin, B. Z. / Kursevich, I. P. / Sorokin, A. A. et al. | British Library Online Contents | 2010

A method of strength assessment of WWER reactor internals by the criterion of stress corrosion cracking in irradiated austenitic steels

Margolin, B. Z. / Fedorova, V. A. / Filatov, V. M. | British Library Online Contents | 2012

Lifetime analysis of wwer reactor pressure vessel internals concerning material degradation

Dudra, J. / Szávai, S. | British Library Online Contents | 2010

Neutron Embrittlement of WWER Reactors: EC-Supported Projects

Ahlstrand, R. / Bieth, M. / Rieg, C. | British Library Online Contents | 2004