Core design study on CANDU-SCWR with 3D neutronics/thermal-hydraulics coupling-Reference-Cited by-同舟云学术

Core design study on CANDU-SCWR with 3D neutronics/thermal-hydraulics coupling

Published:2011-12 Issue:12 Volume:241 Page:4714-4719
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Yang Ping,Cao Liangzhi,Wu Hongchun,Wang Changhui

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

Reference11 articles.

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2. Fuel channel designs for the CANDU-SCWR;Chow,2007

3. Conceptual design of a high temperature power reactor cooled and moderated by supercritical light water;Dobashi,1998

4. Supercritical water-cooled pressure channel nuclear reactors: review and status;Duffey,2005

5. CANDU and generation IV system;Duffey,2004

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