中文摘要：

行波堆可使用低富集度核燃料达到较高的燃耗，核废料不需再回收处理，是闭式燃料循环外有效的核燃料利用体系。为进一步挖掘行波堆在核燃料利用方面的优势，本文对行波堆嬗变次锕系核素（MA）进行了可行性分析。在自主设计的1250Mwt棋盘式径向倒料钠冷行波堆中均匀添加MA，质量份额从2．0％至12．0％。采用自主开发的MCNP—ORIGEN耦合燃耗计算程序进行分析计算。结果表明，MA嬗变量随MA质量份额的增大线性增大，而嬗变率随MA质量份额的增大呈抛物线变化。同时研究了MA质量份额对堆芯安全参数的影响，如堆芯有效增殖因数、多普勒反馈系数、空泡系数和有效缓发中子份额等。计算结果表明，堆芯有效增殖因数和空泡系数随MA质量份额的增大而增大，多普勒反馈系数和有效缓发中子份额随MA质量份额的增大而减小。

英文摘要：

TWR can make use of non-enriched fuel and obtain very high burnup without the need of fuel reprocessing. TWR is an effective way of fuel utilization besides the closed fuel cycle. In this paper, the feasibility of MA transmutation in a TWR was analyzed to further excavate the fuel utilization of this type of reactor. MA was homogeneously charged in the self-designed 1 250 MWt board type radial fuel shuffling sodium cooled TWR core, and the MA weight fraction is from 2.0% to 12.0%. A self developed MCNP-ORIGEN coupled code was applied to perform burnup calculation. The results indicate that the transmutation amount increases linearly with the MA weight fraction, while the transmutation rate parabolically varies with the increase of the MA weight fraction. Neutronic safety parameters, such as the core effective multiplication factor, Doppler feedback coefficient, void worth coefficient and effective delayed neutron fraction, were compared under different MA weight fractions. The results indicate that the core effecti increase with the MA weight effective delayed neutron fract ve multiplication factor and the void worth coeff fraction, while the ion decrease with th Doppler feedback coefficient an lclent d the e increase of the MA weight fraction.