Discussion on the accident behavior and accident management of the HTGR-Reference-Cited by-同舟云学术

Discussion on the accident behavior and accident management of the HTGR

Published:2020-04 Issue: Volume:360 Page:110497
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Zhipeng Chen,Yan Wang,Yanhua Zheng

Funder

National S&T Major

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.

1. FSAR, 2015. (Final Safety Analysis Report) of HTR-PM, INET, Tsinghua University.

2. Fuel performance and fission product behavior in gas cooled reactor. IAEA-TECDOC-978 (ISSN 1011-4289), IAEA, VIENNA, 1997.

3. IAEA Safety Standards. Safety of nuclear power plants: design. Specific Safety Requirements, No. SSR-2/1, 2016.

4. The consequences of water ingress into the primary circuit of a HTR-Module-from design basis accident to hypothetical postulates;Lohnert;Nucl. Eng. Des.,1992

5. PSAR, 2008. (Preliminary Safety Analysis Report) of HTR-PM, INET, Tsinghua University.

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