乏燃料后处理厂强放区域退役初始源项调查研究  

Research for initial radiological characterization for decommissioning of high and intermediate radioactivity level's area within reprocessing plant

作　　者：谢小龙[1,2] 吴德慧[1,2] 陈永望[2,3] 王冠 米爱军 王勇 XIE Xiao-long WU De-hui CHEN Yong-wang WANG Guan MI Ai-jun WANG Yong(University of South China, hengyang 421001, China China Nuclear Power Engineering Co, Ltd. Beijing 100840,China Tsinghua University, Beijing 100084,China)

机构地区：[1]南华大学,湖南衡阳421001 [2]中国核电工程有限公司,北京100840 [3]清华大学,北京100084

出　　处：《核科学与工程》2016年第4期539-547,共9页Nuclear Science and Engineering

摘　　要：随着退役治理专项工作的有序推进,我国早期乏燃料后处理等设施现已转入退役关键阶段,获得放射性特性数据等是退役前必须做的重要工作。本文首次依据我国遗留后处理厂退役初始源项调查科研任务,以工程现状、退役对源项的需求和测量技术基础作为出发点,确定了强放区域的调查原则、调查要求,通过系统设计,集成开发了以无损测量方法作为主要调查手段、面向在线工艺系统的放射性特性调查成套测量技术,为后处理厂强放区域退役奠定了源项基础。本文重点论述了总体设计中遇到的关键技术问题,以及如何运用这些技术解决问题。该方法的总体设计思路具有示范作用,可以作为设计复杂退役调查技术决策的重要依据。The early stage construction of spent nuclear fuel reprocessing plant now is entering to the crucial decommissioning phase.RD project upon radiological characterization is priority.According to the project for initial radiological characterization campaign for decommissioning reprocessing plant,this paper gives analytical summary of status and characteristic of legacy spent nuclear fuel reprocessing plant for the first time,decommissioning requirements and technological base for radiological characterization in China was also concerned in,from which determine the principle and requirements for key area characterization.Systematic design and integration for the instrumental device and corresponding machinery equipments was then bring forwarded,utilizing Non-Destructive Assay methodology through remote handling platform to implement the in-situ and on line measurement for conducting efficiency calibration within key area.The methodology for systematic design have exemplary effect to relate RD project for DD characterization,which can be the major reference for Chinese designers＇ decision-making.

关 键 词：乏燃料后处理厂 退役初始源项调查 源项 无损测量 

分 类 号：TL249[核科学技术—核燃料循环与材料]