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...
Main Authors: | , , , , , , |
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Format: | Article |
Language: | English |
Published: |
KeAi Communications Co., Ltd.
2021-01-01
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Series: | International Journal of Advanced Nuclear Reactor Design and Technology |
Subjects: | |
Online Access: | http://www.sciencedirect.com/science/article/pii/S2468605021000065 |