Preliminary study to improve the performance of SCWR-M during loss-of-flow accident-Reference-Cited by-同舟云学术

Preliminary study to improve the performance of SCWR-M during loss-of-flow accident

Published:2016-10 Issue: Volume:307 Page:431-444
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Liu X.J.,Sun C.,Wang Z.D.,Chai X.,Xiong J.B.,Yang Y.H.,Cheng X.

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference14 articles.

1. Chen, Y., Zhao, M., Yang, C., et al. 2013. Experiment of heat transfer of supercritical water in natural circulation with different diameters of heated tubes. In: Proc. 6th International Symposium on Supercritical Water-cooled Reactors (ISSCWR6), March 3–7, Shenzhen, China, ISSCWR6-13097.

2. A mixed core for supercritical water-cooled reactors;Cheng;Nucl. Eng. Technol.,2008

3. A parametric study of the thermal–hydraulic response of supercritical light water reactors during loss-of-feedwater and turbine-trip events;Davis,2003

4. Modification and application of the system analysis code ATHLET to trans-critical simulations;Fu;Ann. Nucl. Energy,2012

5. Gen IV Roadmap, 2002. US DOE Nuclear Energy Research Advisory Commit-tee and the Generation IV International Forum. In: A Technology Roadmap for Generation IV Nuclear Energy Systems. GIF002-00, December 2002. .

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