Transient thermal analysis of IVR strategy under a LB-LOCA based on ASTEC code

A Large-Break Loss of Coolant Accident (LB-LOCA) in a generic, 1000 MWe and 3-loop Chinese Pressurized Water Reactor (PWR) with the In-Vessel corium Retention (IVR) strategy was simulated by using ASTEC V2.1.1. One of the criteria of assessing the validity of IVR is that the decay heat of molten poo...

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Bibliographic Details
Main Authors: Peng Chen, Hui Fu, Pingwen Ou, Dongyu He, Dekui Zhan, Feiye Liao, Chao Guo
Format: Article
Language:English
Published: KeAi Communications Co., Ltd. 2021-01-01
Series:International Journal of Advanced Nuclear Reactor Design and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2468605021000065