Loss of flow accident and its mitigation measures for nuclear systems with SCWR-M-Reference-Cited by-同舟云学术

Loss of flow accident and its mitigation measures for nuclear systems with SCWR-M

Published:2011-12 Issue:12 Volume:38 Page:2634-2644
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Xu Zhihong,Hou Dong,Fu Shengwei,Yang Yanhua,Cheng Xu

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference13 articles.

1. Design options for the safety injection system of korean next generation reactor;Bae;Annals of Nuclear Energy,2000

2. A mixed core for supercritical water-cooled reactor;Cheng;Nuclear Engineering and Technology,2008

3. Ishiwatari, Y., Oka, Y., Koshizuka, S., 2004. Safety design principle of supercritical water cooled reactors. Proceedings of ICAPP ’04, Pittsburgh, PA USA, June 13–17.

4. Safety of super LWR, (II) safety analysis at supercritical pressure;Ishiwatari;Journal of Nuclear Science and Technology,2005

5. Core and sub-channel evaluation of a thermal SCWR;Liu;Nuclear Engineering and Technology,2009

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