Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)

Bibliographic Details
Published in:Nuclear Engineering and Design
Main Authors: Ballesteros, A., Bros, J., Debarberis, L., Sevini, F., Erak, D., Gezashchenko, S., Kryukov, A., Shtrombakh, Y., Goloschapov, S., Ionov, Pytkin, Y., Anikeev, Y., Banyuk, G., Plusch, A., Gillemot, F., Tatar, L., Petrosyan, V.
Format: Article in Journal/Newspaper
Language:English
Published: Elsevier BV 2005
Subjects:
Mechanical Engineering
Waste Management and Disposal
Safety, Risk, Reliability and Quality
General Materials Science
Nuclear Energy and Engineering
Nuclear and High Energy Physics
Arctic
Online Access:http://dx.doi.org/10.1016/j.nucengdes.2004.08.062
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spelling crelsevierbv:10.1016/j.nucengdes.2004.08.062 2023-05-15T14:51:50+02:00 Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA) Ballesteros, A. Bros, J. Debarberis, L. Sevini, F. Erak, D. Gezashchenko, S. Kryukov, A. Shtrombakh, Y. Goloschapov, S. Ionov Pytkin, Y. Anikeev, Y. Banyuk, G. Plusch, A. Gillemot, F. Tatar, L. Petrosyan, V. 2005 http://dx.doi.org/10.1016/j.nucengdes.2004.08.062 https://api.elsevier.com/content/article/PII:S0029549304003176?httpAccept=text/xml https://api.elsevier.com/content/article/PII:S0029549304003176?httpAccept=text/plain en eng Elsevier BV https://www.elsevier.com/tdm/userlicense/1.0/ Nuclear Engineering and Design volume 235, issue 2-4, page 411-419 ISSN 0029-5493 Mechanical Engineering Waste Management and Disposal Safety, Risk, Reliability and Quality General Materials Science Nuclear Energy and Engineering Nuclear and High Energy Physics journal-article 2005 crelsevierbv https://doi.org/10.1016/j.nucengdes.2004.08.062 2022-11-30T23:02:06Z Article in Journal/Newspaper Arctic ScienceDirect (Elsevier - via Crossref) Arctic Nuclear Engineering and Design 235 2-4 411 419
institution Open Polar
collection ScienceDirect (Elsevier - via Crossref)
op_collection_id crelsevierbv
language English
topic Mechanical Engineering
Waste Management and Disposal
Safety, Risk, Reliability and Quality
General Materials Science
Nuclear Energy and Engineering
Nuclear and High Energy Physics
spellingShingle Mechanical Engineering
Waste Management and Disposal
Safety, Risk, Reliability and Quality
General Materials Science
Nuclear Energy and Engineering
Nuclear and High Energy Physics
Ballesteros, A.
Bros, J.
Debarberis, L.
Sevini, F.
Erak, D.
Gezashchenko, S.
Kryukov, A.
Shtrombakh, Y.
Goloschapov, S.
Ionov
Pytkin, Y.
Anikeev, Y.
Banyuk, G.
Plusch, A.
Gillemot, F.
Tatar, L.
Petrosyan, V.
Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)
topic_facet Mechanical Engineering
Waste Management and Disposal
Safety, Risk, Reliability and Quality
General Materials Science
Nuclear Energy and Engineering
Nuclear and High Energy Physics
format Article in Journal/Newspaper
author Ballesteros, A.
Bros, J.
Debarberis, L.
Sevini, F.
Erak, D.
Gezashchenko, S.
Kryukov, A.
Shtrombakh, Y.
Goloschapov, S.
Ionov
Pytkin, Y.
Anikeev, Y.
Banyuk, G.
Plusch, A.
Gillemot, F.
Tatar, L.
Petrosyan, V.
author_facet Ballesteros, A.
Bros, J.
Debarberis, L.
Sevini, F.
Erak, D.
Gezashchenko, S.
Kryukov, A.
Shtrombakh, Y.
Goloschapov, S.
Ionov
Pytkin, Y.
Anikeev, Y.
Banyuk, G.
Plusch, A.
Gillemot, F.
Tatar, L.
Petrosyan, V.
author_sort Ballesteros, A.
title Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)
title_short Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)
title_full Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)
title_fullStr Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)
title_full_unstemmed Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)
title_sort consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (cobra)
publisher Elsevier BV
publishDate 2005
url http://dx.doi.org/10.1016/j.nucengdes.2004.08.062
https://api.elsevier.com/content/article/PII:S0029549304003176?httpAccept=text/xml
https://api.elsevier.com/content/article/PII:S0029549304003176?httpAccept=text/plain
geographic Arctic
geographic_facet Arctic
genre Arctic
genre_facet Arctic
op_source Nuclear Engineering and Design
volume 235, issue 2-4, page 411-419
ISSN 0029-5493
op_rights https://www.elsevier.com/tdm/userlicense/1.0/
op_doi https://doi.org/10.1016/j.nucengdes.2004.08.062
container_title Nuclear Engineering and Design
container_volume 235
container_issue 2-4
container_start_page 411
op_container_end_page 419
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