PWR(U)乏燃料中超铀元素在混合堆快裂变包层内嬗变研究

Research on the Transmutation for Transuranic Isotopes of the PWR(U)-Spent-Fuel in Fast-Fission Blanket of Fusion-Fission Hybdrid Reactor

从中子学角度对ＰＷＲ（Ｕ）乏燃料中的超铀元素（２３８Ｐｕ、２３９Ｐｕ、２４０Ｐｕ、２４１Ｐｕ、２４２Ｐｕ、２４１Ｐｕ、２４３Ａｍ、２３７Ｎｐ、２４４Ｃｍ）在聚变－裂变混合堆快裂变包层内嬗变的可行性进行了研究．利用一维中子输运和燃耗计算程序ＢＩＤＥＣＡＹ对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。

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.