A method of strength assessment of WWER reactor internals by the criterion of stress corrosion cracking in irradiated austenitic steels: Fid-Bau Portal

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.

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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.

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.

Zugriff

Zugriff über TIB

Verfügbarkeit in meiner Bibliothek prüfen

Bestellung bei Subito €

Seitennavigation

Dokumentinformationen

Ähnliche Titel

Exportieren, teilen und zitieren

Dokumentinformationen

Titel:

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

Beteiligte:

Margolin, B. Z. (Autor:in) / Fedorova, V. A. (Autor:in) / Filatov, V. M. (Autor:in)

Erschienen in:

STRENGTH OF MATERIALS C/C OF PROBLEMY PROCHNOSTI ; 44 ; 115-128

Erscheinungsdatum:

01.01.2012

Format / Umfang:

14 pages

ISSN:

0039-2316

Medientyp:

Aufsatz (Zeitschrift)

Format:

Sprache:

Englisch

Klassifikation:

DDC: 620.11

Margolin, B. Z. / Fomenko, V. N. / Sorokin, A. A. | British Library Online Contents | 2010

Lifetime analysis of wwer reactor pressure vessel internals concerning material degradation

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

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

Report on stress-corrosion cracking of austenitic chromium-nickel stainless steels

TIBKAT | 1960

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