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Heat transfer from spent reactor fuels during shipping : a proposed method for predicting temperature distribution in fuel bundles and comparison with experimental data /

机译：运输过程中废反应堆燃料的传热：提出的预测燃料束温度分布的方法，并与实验数据进行比较/

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Watson, J. S.; (Jack Samuel),; 1935-; U.S. Atomic Energy Commission.; Oak Ridge National Laboratory.; Chemical Technology Division.;
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年度 1963
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4. Finite Element Analysis of Heat Transferbetween Spent CANDU Fuel Bundles in Spent Fuel Pools [C] . C.J.Krasnaj, W. Grant Pacific basin nuclear conference . 2014

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5. An earthquake transient method for pebble-bed reactors and a fuel temperature model for TRISO fueled reactors. [D] . Ortensi, Javier. 2009

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6. Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code [O] . Zsolt Elter, Li Pöder Balkeståhl, Erik Branger, 2020

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7. Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility [O] . 1992

机译：潜在储存库废弃物的特点：第4卷，附录4A，美国教育机构的核反应堆;附录4B，教育机构核反应堆的数据表;附录4C，Fort St. Vrain废燃料的补充数据;附录4d，桃底1花费的补充数据;附录4e，快速通量测试设施的补充数据
8. HEAT TRANSFER FROM SPENT REACTOR FUELS DURING SHIPPING:A PROPOSED METHOD FOR PREDICTING TEMPERATURE DISTRIBUTION IN FUEL BUNDLES AND COMPARISON WITH EXPERIMENTAL DATA [R] . J. S. Watson 1963

机译：运输过程中燃烧反应堆燃料的传热：一种预测燃料束温度分布的方法，并与实验数据进行比较

Heat transfer from spent reactor fuels during shipping : a proposed method for predicting temperature distribution in fuel bundles and comparison with experimental data /

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