Thermal conductivity degradation analyses of LWR MOX fuel by the quasi-two phase material model-Reference-Cited by-同舟云学术

Thermal conductivity degradation analyses of LWR MOX fuel by the quasi-two phase material model

Published:2012-10 Issue:10 Volume:49 Page:966-974
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Kosaka Yuji,Kurematsu Shigeru,Kitagawa Takaaki,Suzuki Akihiro,Terai Takayuki

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://www.tandfonline.com/doi/pdf/10.1080/00223131.2012.723178

Reference22 articles.

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3. Power Generation with Plutonium-uranium Mixed Oxide Fuel at Genkai Nuclear Power Station

4. Fujii, H., Teshima, H., Kanasugi, K. and Y. Kosaka, and Y. Arakawa.Final assessment of MOX fuel performance experiment with Japanese PWR specification fuel in the HBWR. Proc. of International LWR Fuel Performance Meeting. September 30–October 3. Paper 1043

5. Nakae, N., Ikehata, H., Baba, T. and K. Kamimura, H. Fujii, and Y. Kosaka.Irradiation behavior of MOX fuel under high burnup. Proc. of 2010 LWR Fuel Performance/TopFuel/WRFPM. September26–29. Paper 007

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