Study on evaluation method of kernel migration of TRISO fuel for High Temperature Gas-cooled Reactor

Author:

Fukaya Yuji,Okita Shoichiro,Sasaki Koei,Ueta Shohei,Goto Minoru,Ohashi Hirofumi,Yan Xing L.

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

Reference18 articles.

1. ANSYS, Inc. 2013. ANSYS Mechanical APDL Theory Reference. ANSYS, Inc.

2. Fujimoto, N., Nojiri, N., Takeda, E., et al., 2000, Control Rod Position and Temperature Coefficients in HTTR Power-rise Tests -Interim Report-, Japan Atomic Energy Research Institute, JAERI Tech 2000-091. [in Japanese].

3. Fukuda, K., Ogawa, T., Kashimura, S. et al., 1989. Research and development of HTGR fuels. Japan Atomic Energy Research Institute, JAERI-M 89-007. [in Japanese].

4. Carbon Thermal Diffusion in the UC2‐C System;Gulden,1971

5. Assessment of Fuel Integrity of the High Temperature Engineering Test Reactor (HTTR) and its Permissible Design Limit;Hayashi,1989

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