Application of the French Codes to the Pressurized Thermal Shocks Assessment

The integrity of a reactor pressure vessel (RPV) related to pressurized thermal shocks (PTSs) has been extensively studied. This paper introduces an integrity assessment of an RPV subjected to a PTS transient based on the French codes. In the USA, the “screening criterion” for maximum allowable embr...

Full description

Bibliographic Details
Main Authors: Mingya Chen, Guian Qian, Jinhua Shi, Rongshan Wang, Weiwei Yu, Feng Lu, Guodong Zhang, Fei Xue, Zhilin Chen
Format: Article
Language:English
Published: Elsevier 2016-12-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573316300961