Plate spent fuel burnup measurement equipment based on a compact D-D neutron generator  

作　　者：Yi-Nong Li Zheng Wei Gen-Tao Gao Lu Wu Kang Wu Jun Ma Xing-Yu Liu Ze-En Yao Yu Zhang Jun-Run Wang Xiao-Dong Su Zhi-Yong Deng Guo-Rong Wan 

机构地区：[1]School of Nuclear Science and Technology,Lanzhou University,Lanzhou 730000,China [2]Engineering Research Center for Neutron Application,Ministry of Education,Lanzhou University,Lanzhou 730000,China [3]Frontiers Science Center for Rare Isotopes,Lanzhou University,Lanzhou 730000,China [4]Nuclear Power Institute of China,Chengdu 610000,China [5]Wuhan Second Ship Design and Research Institute,Wuhan 430205,China

出　　处：《Nuclear Science and Techniques》2025年第3期189-200,共12页核技术(英文)

基　　金：supported by the National Natural Science Foundation of China(No.12075105);the Major Science and Technology Projects of Gansu Province(No.22ZD6GB020);the NSFC-Nuclear Technology Innovation Joint Fund(No.U2167203);the Fundamental Research Funds for the Central Universities(lzujbky-2023-stlt01,lzujbky-2024-jdzx10)。

摘　　要：Burnup measurement is crucial for the management and disposal of spent fuel.The conventional approach indirectly estimates burnup by examining the fission product or actinide content.Compared to the first two methods,the active neutron method exhibits a lower dependence on the irradiation history and initial enrichment degree of the spent fuel.In addition,it can be used to directly determine the content of fissile nuclides in spent fuel.This study proposed the design of a burnup measurement equipment specifically crafted for plate segments by utilizing a compact D-D neutron generator.The equipment initiates the fission of fissile nuclides within the spent fuel plate segment through thermal neutrons provided by the moderators.Subsequently,the burnup is determined by analyzing the transmitted thermal neutrons and counting the fission fast neutrons.The Monte Carlo program Geant4 was used to simulate the relationship between spent fuel plate segment assembly burnup and the detector count of 10 MW material test reactor designed by the International Atomic Energy Agency.Consequently,the feasibility of the method and rationality of the detector design were verified.

关 键 词：Burnup measurement Plate spent fuel Active neutrons 

分 类 号：O57[理学—粒子物理与原子核物理]