Ductile crack initiation under mechanical and thermal loads

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Authors: Yoshio Urabe, I. Mitsutaka, Kiminobu Hojo, Yoshinori Hashimoto
Cited by: 0

Abstract

The emergency core cooling system (ECCS) operates when a hypothetical severe thermal transient occurs in a nuclear reactor pressure vessel and the hot wall of pressure vessel is cooled by cold ECCS water. At this time, the vicinity of the inner surface is subjected to high thermal stresses owing to constraint of components and temperature gradients. Especially, under the pressurized thermal shock (PTS) condition, the membrane stress induced by pressure is added. PTS problem is one of the most important issues for integrity of the nuclear reactor pressure vessel.

Fields of Study & Subjects

Metal Forming Simulation Techniques Advanced Surface Polishing Techniques Metallurgy and Material Forming

Publication details

Pages
381–386
Publication date
17 February 2026
Language
EN
Document type
Book chapter