ESBWR passive safety system performance under loss of coolant accidents-Reference-Cited by-同舟云学术

ESBWR passive safety system performance under loss of coolant accidents

Published:2017-04 Issue: Volume:96 Page:1-17
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Rassame Somboon,Hibiki Takashi,Ishii Mamoru

Funder

U.S. Nuclear Regulatory Commission

U.S. Government

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference28 articles.

1. ESBWR Design Description;Bautista,2002

2. Simplified Boiling Water Reactor (SBWR) Program – Gravity-driven Cooling System (GDCS) Integrated Systems Test – Final Report;Billig,1989

3. GIRAFFE SBWR Systems Interactions Test Report;Duncan,1996

4. Gamble, R.E., et al. Pressure scaling analysis of the SBWR and Integral test facilities–post test review. In: Proceedings of ICONE5: 5th International Conference on Nuclear Engineering, ICONE5-2073, May 26–30, 1997, Nice, France

5. ESBWR Technology Program: Test Program;Gamble,2002

Cited by 18 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. Numerical Research on Aerosol Transport and Deposition Inside a Heat Exchanger Tube Based on Lagrange Methodology;Aerosol Science and Engineering;2024-06-24

2. Analysis of main steam line break accident on a BWR test facility using TRACE;Nuclear Engineering and Design;2024-01

3. Safety Margins Improvement by Means of the Passive Heat Removal System and the Ha-2 in Vver-1000/V320 Reactors;2024

4. Application of Data-Driven technology in nuclear Engineering: Prediction, classification and design optimization;Annals of Nuclear Energy;2023-12

5. 1D modelling and preliminary analysis of the coupled DYNASTY–eDYNASTY natural circulation loop;Frontiers in Energy Research;2023-04-11