Research on scaling analysis and design parameters of integral test facilities for PWR-Reference-Cited by-同舟云学术

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Research on scaling analysis and design parameters of integral test facilities for PWR

Published:2021-12 Issue: Volume:163 Page:108557
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Li Liangguo,Long Biao,Yu Jianming,Su Qianhua,Lu Donghua,Wu Yingwei,Qiu Suizheng,Su Guanghui,Tian Wenxi,Wu Xiaohang,Liu Jiyong,Ju Peng

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference76 articles.

1. American Nuclear Society. 2014. Decay Heat Power in Light Water Reactors. La Grange. IL. ANSI/ANS-5.1.

2. Comparison of three SBLOCA tests with different break locations using the SMART-ITL facility to estimate the safety of the SMART design;Bae;Nucl. Eng. Technol.,2017

3. KAERI integral effect test program and the ATLAS design;Baek;Nucl. Technol.,2005

4. Scaling in the safety of next generation reactors;Banerjee;Nucl. Eng. Des.,1998

5. Investigation of PWR accident situations at BETHSY facility;Bazin;Nucl. Eng. Des.,1990

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor;Nuclear Engineering and Design;2024-08

2. Experimental research and theoretical analysis of flow instability in advanced secondary passive residual heat removal system;Annals of Nuclear Energy;2023-06

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