Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)
Published in: | Nuclear Engineering and Design |
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Main Authors: | , , , , , , , , , , , , , , , , |
Format: | Article in Journal/Newspaper |
Language: | English |
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Elsevier BV
2005
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Online Access: | 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 |
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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 |
_version_ |
1766322986286055424 |