压水堆嬗变MA安全性研究

The Safety Characteristics of Transmutation MA in PWR

摘要: 压水堆可嬗变长寿命次锕系核素，本文通过BEAVRS基准堆芯搭建、MA核素装载方案设计、NJOY温度截面库制作、硼浓度调节各过程，在临界状态下计算堆芯反应性、中子通量及能谱、温度系数等相关参数，展开在压水堆燃料棒上镀层MA核素的嬗变研究。计算结果表明：在3.1%富集度区域全镀层0.0025 cm厚度MA核素；在2.4%富集度区域全镀层0.0015 cm厚度MA核素；在最外围和第二外围区域镀层0.002 cm厚度MA核素，此三种装载方式具有更优的可行性，且均不会对堆芯安全性能产生不利影响。本文为进一步计算嬗变率、确定最优化装载方案提供了可靠的数据支持，具有参考价值。

Abstract: Pressurized water reactor can transmute long-lived minor actinides. In this paper, the characte-ristics of transmutation MA on PWR fuel rods are studied via establishing BEAVRS core model, designing MA nuclides coating patterns, making temperature cross section library by NJOY, and adjusting boric acid concentration. We also calculate the reactivity, neutron flux and spectrum, temperature coefficients and other parameters at the critical state. The results show that there are three loading patterns which are more feasible, and none of them have adverse effects on the core safety performance. We list these three patterns as follows. Loading MA nuclides with coating thickness of 0.0025 cm in 3.1% enrichment fuel area; Loading MA nuclides with coating thickness of 0.0015 cm in 2.4% enrichment fuel area; Loading MA nuclides with coating thickness of 0.002 cm in the outermost and the second outermost area. This paper provides reliable data reference for further calculation of transmutation rate and determination of optimal loading pattern.