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Irradiation Experiment of MOX Fuel Assembly for Advanced Thermal Reactor.

机译：高压热反应器MOX燃料组件的辐照试验。

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Shinichi UEMATSU; Takeshi MITSUGI; Keiichi KIKUCHI; Tetsurou KOBAYASHI; Jun YOKOYA;
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年度 1997
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机译：在先进的热反应器中辐照到高燃耗的MOX燃料棒中燃料-包层的化学相互作用
2. Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II [J] . Garner F.A., Makenas B.J., Chastain S.A. Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2011,第1期

机译：从EBR-II辐照的三个MOX燃料组件的AISI 304燃料销包壳中观察到膨胀和蠕变
3. Analysis of core physics experiments on irradiated BWR MOX fuel in the REBUS program [J] . Toru Yamamoto, Yoshihira Ando, Yamato Hayashi, Journal of nuclear science and technology . 2012,第1a2期

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5. Optimal fuel management of CANDU reactors at approach to refuelling equilibrium: An investigation into the optimal use of advanced fuels in the CANDU-6 reactor. [D] . Tingle, Christopher Paul. 1998

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6. Thermally-Conductive and Mechanically-Robust Graphene Nanoplatelet Reinforced UO2 Composite Nuclear Fuels [O] . Tiankai Yao, Guoqing Xin, Spencer Michael Scott, -1

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Irradiation Experiment of MOX Fuel Assembly for Advanced Thermal Reactor.

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