Post-test analysis of helium circulator trip without scram at 3MW power level on the HTR-10-Reference-Cited by-同舟云学术

Post-test analysis of helium circulator trip without scram at 3MW power level on the HTR-10

Published:2009-06 Issue:6 Volume:239 Page:1010-1018
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chen F.,Dong Y.,Zhang Z.,Zheng Y.,Shi L.,Hu S.

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

Reference16 articles.

1. Simulation and analysis of helium circulator trip ATWS test at full power on the HTR-10;Dong,2008

2. Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core;Gao;Nucl. Eng. Des.,2002

3. Thermal hydraulic transient analysis of the HTR-10;Gao;Nucl. Eng. Des.,2002

4. Results of experiments at the AVR reactor;Gottaut;Nucl. Eng. Des.,1990

5. Thermal response of a modular HTR under accident conditions;Haque;Nucl. Energ. -J. Br. Nucl.,1983

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