Structural design of ceramic internals of HTR-10-Reference-Cited by-同舟云学术

Structural design of ceramic internals of HTR-10

Published:2002-10 Issue:1-3 Volume:218 Page:123-136
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Zhang Zhensheng,Liu Junjie,He Shuyan,Zhang Zhengming,Yu Suyuan

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

Reference6 articles.

1. Simulation tests for temperature mixing in a core bottom model of the HTR-module;Damm;Nucl. Eng. Des.,1992

2. Design and qualification of components for high-temperature reactor;Dumm;Nucl. Eng. Des.,1990

3. Passive heat removal from the core of small and medium sized pebble bed reactor;Kugeler;Nucl. Eng. Des.,1992

4. Matsuo, H., Nomura, S., Imat, H., et al., Effects of high temperature neutron irradiation on the physical, chemical and mechanical properties of fine-grained isotropic graphite. IAEA Specialists Meeting on Graphite Component Structural Design, JAERI Tokai, Japan, JAERI-M 86-192, January 1987.

5. Structural design criteria for HTR—a summary report;Schubert;Nucl. Eng. Des.,1991

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