公开(公告)号：US20240221966A1

公开(公告)日：2024-07-04

申请号：US18608909

申请日：2024-03-18

申请人： Xi'an Jiaotong University

发明人： Di Yun ,  Yiwei Zhao ,  Jie Qiu ,  Yi Le ,  Haibin Mu ,  Yijia Luo ,  Xinlu Gu ,  Shuang Xiang ,  Wenbo Liu

IPC分类号： G21F5/10 ,  G21C17/06

CPC分类号： G21F5/10 ,  G21C17/06

摘要： The present disclosure provides a method for pre-separating nuclides in spent fuel, comprising steps: S1. generating a temperature of 1200 to 1600° C. in a center of a fuel element, and at the same time introducing a cooling medium to an outer surface of the fuel element, to introduce a temperature difference to heat the fuel element; S2. soaking cooled spent fuel in an ionic liquid to selectively dissolve fission products and transuranic elements, so that the fission products and the transuranic elements are pre-separated from the spent fuel. The method achieves the effect of pre-separating part of the fission products and transuranic elements by physical methods, and solves the problem that homogenization in traditional post-processing technology causes obstacles to nuclide separation.