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

• Published in: Journal of nuclear materials Vol. 596; p. 155055
• Main Authors: Cattivelli, Alessandro, Burke, Mary Grace, Dhers, Jean, Francis, John Anthony
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.08.2024
• Subjects: Ductile-to-brittle transition; Grain boundary embrittlment; Post weld heat treatment; Segregation; Structural integrity; Submerged-arc strip cladding; Structural integrity; Ductile-to-brittle transition; Submerged-arc strip cladding; Post weld heat treatment; Segregation; Grain boundary embrittlment

Underclad cracking in nuclear pressure vessels was of significant concern in the 1970s and 1980s before mitigating adjustments were made both to steel compositions and manufacturing practice. Unfortunately, the cracking mechanisms are still not well understood, and this can undermine confidence when...