Mechanical behavior of high-Ni/high-Mn Barsebäck 2 reactor pressure vessel welds after 28 years of operation-Reference-Cited by-同舟云学术

Mechanical behavior of high-Ni/high-Mn Barsebäck 2 reactor pressure vessel welds after 28 years of operation

Published:2023-08 Issue: Volume:581 Page:154447
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Lindqvist Sebastian^ORCID,Norrgård Alex^ORCID,Arffman Pentti^ORCID,Hytönen Noora^ORCID,Lydman Jari^ORCID,Efsing Pål^ORCID,Suman Siddharth,Nevasmaa Pekka

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference37 articles.

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3. W.L. Server, M. Brumovský, International review of nuclear reactor pressure vessel surveillance programs. STP1603, 2018. https://doi.org/10.1520/stp1603-eb.

4. Standard practice for design of surveillance programs for light-water moderated nuclear power reactor vessels. ASTM E185-16,2016

5. Influence of Ni-Mn contents on the embrittlement of PWR RPV model steels irradiated to high fluences relevant for LTO beyond 60 years;Kolluri;J. Nucl. Mater.,2021

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1. On comparison of fracture toughness of irradiated and thermally aged decommissioned nuclear weld metals with miniature specimen test technique;Theoretical and Applied Fracture Mechanics;2024-10

2. Microscopic Characterisation of Brittle Fracture Initiation in Irradiated and Thermally Aged Low-Alloy Steel Welds of a Decommissioned Reactor Pressure Vessel;2024

3. Elemental distribution in a decommissioned high Ni and Mn reactor pressure vessel weld metal from a boiling water reactor;Nuclear Materials and Energy;2023-09