等效天然铀入堆辐照试验中子学性能分析

本文基于重水堆堆芯核设计程序系统，计算分析了装入等效天然铀（NUE）燃料的试验堆芯的中子学性能。对选择两个燃料通道进行入堆试验的方案进行了论证分析，通过与相应的设计限值以及全天然铀（NU）燃料堆芯中子学性能的比较，检验了实际入堆NUE燃料的中子学等效性。研究表明，实际入堆NUE燃料满足燃料的等效性要求，两个NUE燃料通道入堆试验方案从核设计角度是可行的，堆芯安全性不受影响。

Neutronics Behavior Analysis for Natural Uranium Equivalent Fuel Test Irradiation

The neutronics behavior of the test reactor core fuelled with natural uranium equivalent （NUE） was analyzed based on the neutronics design code system for CANDU reactor. The NUE two-channel test reactor core was demonstrated, and the analysis results were compared with the safety criteria and neutronics behavior of the corresponding fully natural uranium （NU） filled core to confirm the neutronics equivalence of NUE fuel. The study shows that NUE fuel filled in testing reactor meets the neutronics equivalence requirement. The test irradiation of NUE fuel in two channels of a CANDU reactor core with NU fuel is feasible in the neutronics design, and the introducing NUE has no impact on the core safety assessment.