桶装非均匀核废物中铀钚无损定量分析关键技术研究

项目名称： 桶装非均匀核废物中铀钚无损定量分析关键技术研究

项目编号： No.41274109

项目类型： 面上项目

立项/批准年度： 2013

项目学科： 天文学、地球科学

项目作者： 刘明哲

作者单位： 成都理工大学

项目金额： 70万元

中文摘要： 本项目围绕国家在核废物处理领域的技术需求和关键科学问题，结合自主研制的TGSE-NWD系统，以实现非均匀核废物桶U、Pu核素准确识别和定量分析为主要目标，开展基础性新方法、新技术和应用研究。建立统计分布式DRF模型，提出有效的U、Pu核素复杂γ射线能谱解析算法，并与蒙卡模拟谱相结合，形成能谱数据库。结合核废物桶层析扫描技术，制备代表性非均匀介质，设计具有典型放射性比活度的U、Pu体源模型，开展实验与模拟研究，进行U、Pu核素和137Cs透射源γ射线衰减特征和自吸收特征研究，并建立γ射线衰减校正融合算法和非均匀U、Pu体源自吸收校正模型。开展基于蒙卡模拟的效率刻度和含量刻度技术研究，实现对核废物桶中U、Pu核素准确定性与定量分析。该研究成果预期打破国外技术垄断，解决我国核废物处置中U、Pu核素分析的技术瓶颈，为国家核安全保障和环境保护提供技术和人才支持。

中文关键词： 非均匀核废物；图像重建；层析γ扫描；无损检测；蒙特卡罗模拟

英文摘要： This proposal is closely associated with technological requirements and key scientific issues in the field of nuclear waste disposal. Based on a self-developed TGSE-NWD system,the focus of this proposal is on realizing accurate identification and quantitative analysis of inhomogeneous U and Pu nuclides distributed in nuclear waste drums. The proposal is to develop statistical detector-response-function models, present novel algorithms for complicated gamma spectras arising from U and Pu, and simulate the gamma spectras using the Monte Carlo method to obtain energy spectra database. In this project, we utilize the TGSE-NWD platform, prepare typical inhomogeneous media and design U/Pu body source models with given specific activity to develop experimental and simulation investigations. The main concern of this project is to study (i) characteristic of gamma-ray attenuation and self absorption in U/Pu nuclides and 137Cs radioactive source; (ii) fusion algorithm of gamma-ray linear attenuation correction and self-absorption correction model for inhomogeneous U/Pu body source and (iii) efficency and content scales on the basis of Monte Carlo simulations in order to achieve qualitative and quantitative analysis on U/Pu nuclides in nuclear waste drums as accuracy as possible. Then the software is developed and applied

英文关键词： Nuclear waste；Image reconstruction；Tomographic gamma scanner；Nondestructive assay；Monte Carlo simulations