Physical simulation of the underclad heat affected zone in a reactor pressure vessel to study intergranular cracking-Reference-Cited by-同舟云学术

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Physical simulation of the underclad heat affected zone in a reactor pressure vessel to study intergranular cracking

Published:2024-08 Issue: Volume:596 Page:155055
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Cattivelli Alessandro^ORCID,Burke Mary Grace^ORCID,Dhers Jean^ORCID,Francis John Anthony^ORCID

Funder

Framatome SA

EPSRC

Publisher

Elsevier BV

Reference34 articles.

1. Reheat cracking—a review of recent studies;Dhooge;Int. J. Press. Vessels Piping,1987

2. Reheat cracking metallurgical consideration and mechanisms;Dunand-Roux,1982

3. Enhancement of the quality of the reactor pressure vessel used in light water power plants by advanced material, fabrication and testing technologies;Kussmaul;Int. J. Press. Vessels Piping,1980

4. Comparison of stress relief cracking in A 508 2 and A 533 B pressure vessel steels;Shin;Met. Sci.,1984

5. Structural integrity of nuclear reactor pressure vessels;Knott;Philos. Mag.,2013

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