Application of matrix effect correction method based on NFMG in DDA nuclear safeguard system International Symposium on Symbiotic Nuclear Power (ISSNP2024)

报告详情

Application of matrix effect correction method based on NFMG in DDA nuclear safeguard system

编号：92 访问权限：私有更新：2024-09-17 16:30:21 浏览：133次口头报告

报告开始：暂无开始时间（Asia/Shanghai）

报告时间：暂无持续时间

所在会场：[暂无会议] [暂无会议段]

演示文件

提示：该报告下的文件权限为私有，您尚未登录，暂时无法查看。

摘要

The purpose of implementing matrix correction is to compensate for the fissile nuclide mass measurement deviation caused by the matrix effect within a limited time frame. In previous work, we introduced a novel matrix correction method using the neutron flux monitor group (NFMG) response and applied it to an active neutron interrogation (ANI) system based on the delayed neutron. This method can be used to identify the known matrix by an improved simulated annealing (SA) algorithm and to correct the unknown matrix by fitting the equation. In this work, we further extend this method to ANI systems based on differential die-away (DDA) methods. To validate again the applicability and accuracy of the correction method, a DDA equipment model and various matrix compositions were developed using the Geant4 toolkit. The results demonstrate that for U₃O₈ materials with varying enrichment and distribution, the improved SA algorithm can still efficiently identify the various matrix materials in the reference database, and the identification rate is not less than 94.6%. Moreover, the average relative deviation of the corrected ²³⁵U mass is no more than 34.0% for the unknown matrix. This work effectively demonstrates the universality of the matrix correction method based on NFMG response for different ANI systems.