Spontaneous stabilization of HTGRs without reactor scram and core cooling—Safety demonstration tests using the HTTR: Loss of reactivity control and core cooling-Reference-Cited by-同舟云学术

Spontaneous stabilization of HTGRs without reactor scram and core cooling—Safety demonstration tests using the HTTR: Loss of reactivity control and core cooling

Published:2014-05 Issue: Volume:271 Page:379-387
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Takamatsu Kuniyoshi,Yan Xing L.,Nakagawa Shigeaki,Sakaba Nariaki,Kunitomi Kazuhiko

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

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3. Investigation of the loss of forced cooling test by using the high temperature engineering test reactor (HTTR) (Contract research), JAERI-Tech 2007-056;Nakagawa,2007

4. SRAC2006: a comprehensive neutronics calculation code system, JAERI-data/code 2007-004;Okumura,2007

5. Design of High Temperature Engineering Test Reactor (HTTR), JAERI 1332;Saito,1994

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