等效天然铀燃料中子学性能分析

Neutronic Behavior Analysis on Natural Uranium Equivalent Fuel

采用10种回收铀(RU)和贫铀(DU)成分情形,根据等效天然铀(NUE)燃料混合比计算程序ALPHA算得配成NUE燃料的混合比。以标准CANDU 6栅元结构为载体,采用WIMS程序,通过比较NUE燃料与天然铀(NU)燃料的中子学性能参数,以及NUE燃料入堆示范验证试验中实际入堆的燃料信息,对NUE燃料与NU燃料的中子学性能等效性进行了论证分析。研究表明,与NU燃料相比,各种情形下NUE燃料在无限增殖系数、卸料燃耗、冷却剂空泡反应性以及燃料温度效应等中子学性能参数上吻合较好,NUE燃料与NU燃料具备较好的中子学等效性,可应用于重水堆核电站,实现回收铀的有效利用。

This paper expresses an interest in using recycled uranium（RU） in heavy water reactors.Using the data of recycled uranium and depleted uranium（DU） provided by IAEA,and the information of natural uranium equivalent（NUE） fuel loaded in reactor core,the program ALPHA was used to adjust the RU/DU radio to get NUE fuel compositions.Based on the standard bundle cell carrier of CANDU 6,the k∞,exit burnup,coolant void reactivity（CVR） and fuel temperature coefficient of NUE were evaluated and compared with those of NU.It shows neutronics equivalent of the NUE fuel with the corresponding nominal NU fuel.