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HTGR fuels and core development program. Quarterly progress report for the period ending February 28, 1977. Graphite and fuel irradiation; fission product release

机译：HTGR燃料和核心开发计划。截至1977年2月28日止期期间的季度进度报告。石墨和燃料辐照;裂变产品释放

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1. Computational analysis of modern HTGR fuel performance and fission product release during the HFR-EU1 irradiation experiment [J] . Karl Verfondern, Andre Xhonneux, Heinz Nabielek, Nuclear Engineering and Design . 2014,第jula期

机译：HFR-EU1辐射实验中现代HTGR燃料性能和裂变产物释放的计算分析
2. Studies of Ceramic Fuels with the Use of Fission Gas Release Loop, (I)Fission Gas Release from UO2-Graphite Mixture during Irradiation [J] . Seishi YAJIMA, Yuichiro KAMEMOTO, Muneo HAND, Journal of nuclear science and technology . 1967,第4期

机译：使用裂变气体释放回路对陶瓷燃料的研究，（I）辐照过程中UO2-石墨混合物中裂变气体的释放
3. Fission Gas Release from Nuclear Fuels, (II)Fission Gas Release from Nuclear Fuels during Low Temperature, Low Dose Irradiation [J] . Yasutaka OSAWA Journal of nuclear science and technology . 1965,第8期

机译：核燃料释放的裂变气体（II）低温，低剂量辐照期间核燃料产生的裂变气体
4. FISSION PRODUCT RELEASE FROM HTGR FUEL UNDER CORE HEATUP ACCIDENT CONDITIONS [C] . Karl Verfondern, Heinz Nabielek International topical meeting on high temperature reactor technology;HTR 2008 . 2009

机译：核心热事故条件下高温气冷堆燃料的裂变产物释放
5. A model for fuel oxidation and diffusion-based fission product release under severe nuclear reactor accident conditions [D] . Purdy, Peter Leon 1995

机译：严重核反应堆事故工况下基于燃料氧化和扩散的裂变产物释放的模型
6. HTGR Fuels and Core Development Program. Quarterly progress report for the period ending August 31, 1977. Graphite and fuel irradiation; fission product release [O] . 1977

机译：HTGR燃料和核心开发计划。截至1977年8月31日止期期间的季度进度报告。石墨和燃料辐照;裂变产品释放

HTGR fuels and core development program. Quarterly progress report for the period ending February 28, 1977. Graphite and fuel irradiation; fission product release

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