Numerical Investigation on the Thermal-Hydraulic Characteristics near a Corroded Lower Head of the Reactor Vessel During IVR-ERVC
Author:
Affiliation:
1. Shanghai University of Electric Power, College of Energy and Mechanical Engineering, Shanghai, China
2. Nuclear Power Institute of China, Science and Technology on Reactor System Design Technology Laboratory, Chengdu, China
Funder
National Natural Science Foundation of China
Shanghai Sailing Program
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2022.2143208
Reference27 articles.
1. Effect of the heat transfer liquid fin on critical heat flux enhancement under ERVC condition
2. In-vessel retention of corium at the Loviisa plant
3. In-vessel coolability and retention of a core melt
4. Overview of in-vessel retention concept involving level of passivity: With application to evolutionary pressurized water reactor design
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