Structure and thermal properties of as-fabricated U-7Mo/Mg and U-10Mo/Mg low-enriched uranium research reactor fuels

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• 作者：Mykola Kulakov^a ; ^{mykola.kulakov@cnl.ca} ; ^{mykola.kulakov@gmail.com} ; Mouna Saoudi^a ; Markus H.A. Piro^b ; Ronald L. Donaberger^c
• 关键词：Low-enriched uranium research reactor fuel ; Uranium-molybdenum ; Magnesium matrix ; Microstructure ; Thermal properties ; In-reactor fuel temperature
• 刊名：Journal of Nuclear Materials
• 出版年：2017
• 出版时间：February 2017
• 年：2017
• 卷：484
• 期：Complete
• 页码：288-296
• 全文大小：3091 K
• 卷排序：484

文摘

Neutron diffraction analysis shows that most of the γ-U(Mo) phase was retained in as-fabricated U-7Mo/Mg and U-10Mo/Mg fuel cores. The experimental thermal conductivity of both types of fuel is practically identical. Based on conjugate heat transfer simulations, under normal operating conditions, the in-reactor fuel centreline temperature is about 510 K.