| PWR（U）乏燃料中超铀元素在混合堆快裂变包层内嬗变研究 |
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| 引用本文： | 杨永伟,邱励俭.PWR（U）乏燃料中超铀元素在混合堆快裂变包层内嬗变研究[J].核动力工程,1995,16(1):40-45. |
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| 作者姓名： | 杨永伟 邱励俭 |
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| 作者单位： | 中国科学院等离子体物理研究所 |
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| 摘 要： | 从中子学角度对ＰＷＲ（Ｕ）乏燃料中的超铀元素（２３８Ｐｕ，２３９Ｐｕ，２４１Ｐｕ，２４１Ａｍ，２４３Ａｍ，２３７Ｎｐ，２４４Ｃｍ）在聚变－裂变混合堆快裂变包层内嬗变的可行性进了研究。利用一维中子输运和燃耗计算程序ＢＩＤＥＣＡＹ译不同燃料组分的四个快裂变包层进行分析计算。结果表明，在聚变－裂变混合堆快裂变包层内安全，高效地嬗变ＰＷＲ（Ｕ）乏燃料中的超铀元素是可能的。
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| 关 键 词： | PWR（U）乏燃料 超铀元素 快裂变包层 嬗变 |
Research on the Transmutation for Transuranic Isotopes of the PWR(U)-Spent-Fuel in Fast-Fission Blanket of Fusion-Fission Hybdrid Reactor |
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| Yang Yongwei, Qiu Lijian.Research on the Transmutation for Transuranic Isotopes of the PWR(U)-Spent-Fuel in Fast-Fission Blanket of Fusion-Fission Hybdrid Reactor[J].Nuclear Power Engineering,1995,16(1):40-45. |
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| Authors: | Yang Yongwei Qiu Lijian |
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| Abstract: | It is studied frome the point of view of neutronics that feasibility of transmutation for transuranic isotopes of the PWR(U)-Spent-Fuel including 238Pn, 239Pn, 240pn, 241Pn, 242Pn,241Am, 243Am arid 244Cm in the Fast-Fission-Blanket of Fusion-Fission Hybrid Reactor. The neutron transport and burnup of four Fast-Fission-Blankets with various fuel composition has been calculated and analyzed using the one-dimension-neutron-transpo non-code BIDECAY. The results show that it is possible to transmute the transuranic isotopes of the PWR(U)-Spent-Fuel with reliable safety and high efficiency in the Fast--Fission-Blanket of Fusion-Fission Hybrid Reactor. |
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| Keywords: | PWR(U)-Spent-Fuel Transuranic isotopes Fusion-Fission Hybrid Reactor Fast-Fission-Blanket Transmutation |
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