可逆比热容法测量反应堆中子注量率的可行性及应用前景  

Feasibility and Application Prospect of Reversible Specific Heat Capacity Method for Measuring Neutron Fluence Rate of Reactor

作　　者：杨铜锁[1] 朱庆福[2] 史永谦[2] 辛督强[1] 张建祥[1] 王璠[2] 王永仓[1] 鲁谨[2] YANG Tongsuo;ZHU Qingfu;SHI Yongqian;XIN Duqiang;ZHANG Jianxiang;WANG Fan;WANG Yongcang;LU Jin(Shaanxi Engineering Research Center of Controllable Neutron Source,Xijing University,Xi＇an 710123,China;China Institute of Atomic Energy,P.O.Box 275 45,Beijing 102413,China)

机构地区：[1]西京学院陕西省可控中子源工程技术研究中心,陕西西安710123 [2]中国原子能科学研究院反应堆工程技术研究部,北京102413

出　　处：《原子能科学技术》2018年第12期2289-2295,共7页Atomic Energy Science and Technology

基　　金：国家自然科学基金资助项目(11175267;11775310)

摘　　要：热分析仪器和测量技术的迅速发展为通过测量受辐照材料热性质的变化测量中子注量提供了可能。本文提出采用调制差示扫描量热(MDSC)法测量反应堆辐照的含硼材料可逆比热容的变化,进而得到反应堆的中子注量率。从理论和实验两方面讨论了利用该方法测量反应堆中子注量率的可行性。介绍了可逆比热容法测量反应堆中子注量率的原理和实验方法。展望了这种测量方法在测量高注量反应堆中子注量率的应用前景。With the rapid development of thermal analysis instrument and measurement technology,it is possible to measure neutron fluence by measuring the change of thermal properties of irradiated materials.In this paper,the modulated differential scanning calorimetry（MDSC）method was adopted to measure the neutron fluence rate of the reactor with the change of the reversible specific heat capacity of the boron containing materials irradiated in the reactor.The feasibility of this method to measure neutron fluence rate in the reactor was discussed in both theory and experiment.The principle and experimental method for measuring neutron fluence rate in the reactor by reversiblespecific heat capacity method were introduced in detail.The application of this method in measuring the neutron fluence rate of high fluence reactor is prospected in the future.

关 键 词：固体核径迹探测器 热分析 中子注量率 调制差示扫描量热法 可逆比热容 

分 类 号：O571.53[理学—粒子物理与原子核物理]