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

杨铜锁; 朱庆福; 史永谦; 辛督强; 张建祥; 王璠; 王永仓; 鲁谨

doi:10.7538/yzk.2018.youxian.0152

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

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

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- 刊出日期: 2018-12-19

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

1.
Shaanxi Engineering Research Center of Controllable Neutron Source, Xijing University, Xi’an 710123, China
2.
China Institute of Atomic Energy, P. O. Box 27545, Beijing 102413, China

摘要

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。
- 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
Abstract: 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 reversible specific 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.
- solid nuclear track detector ,
- thermal analysis ,
- neutron fluence rate ,
- modulated differential scanning calorimetry method ,
- reversible specific heat capacity

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参考文献(16)

[1]	马鹏飞，阮永丰，洪晓丰，等. 中子辐照对6H-SiC晶体比热容的影响[J]. 硅酸盐学报，2009，37(4)：605-608. MA Pengfei, RUAN Yongfeng, HONG Xiaofeng, et al. The effect of neutron-irradiation on specific heat capacity of 6H-SiC[J]. Journal of the Chinese Ceramic Society, 2009, 37(4): 605-608(in Chinese).
[2]	于效忠，吕国刚，张觐，等. 核辐射物理学[M]. 北京：原子能出版社，1986.
[3]	王广厚. 粒子和固体相互作用物理学[M]. 北京：科学出版社，1991.
[4]	曹建中. 半导体材料的辐射效应[M]. 北京：科学出版社，1993.
[5]	王艳色，魏志勇，申凯华，等. 调制差示扫描量热法在高分子材料中的应用[J]. 高分子通报，2016(3)：16-21.WANG Yanse, WEI Zhiyong, SHEN Kaihua, et al. Application of modulated differential scanning calorimetry in polymer research[J]. Chinese Polymer Bulletin, 2016(3): 16-21(in Chinese).
[6]	RIBEIRO M, GROLIER J P E. Temperature modulated DSC for the investigation of polymer materials: A brief account of recent studies[J]. Journal of Thermal Analysis and Calorimetry, 1999, 57: 253-263.
[7]	解云川，范晓东. 调制式DSC在高聚物研究中的应用[J]. 高分子通报，2002(2)：67-74.XIE Yunchuan, FAN Xiaodong. Applications of modulated differential scanning calorimetry in polymer research[J]. Chinese Polymer Bulletin, 2002(2): 67-74(in Chinese).
[8]	READING M. Method and apparatus for parsed dynamic differential analysis: US, 5474385[P]. 1995.
[9]	READING M, HAHN B K, CROWE B S. Method and apparatus for modulated differential analysis: US, 5346306[P]. 1994.
[10]	READING M, LUGET W R. Modulated differential scanning calorimetry[J]. Thermochimica Acta, 1994, 238(15): 295-307.
[11]	鲁红，冯大春，杨继佑，等. DSC、MDSC测定物质比热容的比较[J]. 分析仪器，2011(3)：70-74.
[12]	杨铜锁，史永谦，朱庆福，等. 利用测热技术测量核反应堆中子通量密度[J]. 原子能科学技术，2016，50（9）：1629-1633.YANG Tongsuo, SHI Yongqian, ZHU Qingfu, et al. Measurement of neutron flux density in reactor with thermal analysis method[J].Atomic Energy Science and Technology, 2016, 50（9）:1629-1633(in Chinese).
[13]	杨铜锁，何少蓉，李天祥，等. 热分析法测量磷灰石中固体核径迹[J]. 科学通报，2009，54(17)：2495-2499.YANG Tongsuo, HE Shaorong, LI Tianxiang, et al. Measurement of nuclear tracks in apatite by thermal analysis method[J]. Chinese Science Bulletin, 2009, 54(17): 2495-2499(in Chinese).
[14]	陈洛娜，包伯荣，李燕飞，等. 用钴活化法测定反应堆中热中子积分通量[J]. 核技术，1988，11(12)：33-35.CHEN Luona, BAO Borong, LI Yanfei, et al. Measurement of integral thermal neutron flux in a high flux reactor by the Co activation method[J]. Nuclear Techniques, 1988, 11(12): 33-35(in Chinese).
[15]	张志军，雷家荣，袁示刚，等. 固体核径迹法测量中子注量的研究[J]. 中国辐射卫生，2006，15(2)：6-9.ZHANG Zhijun, LEI Jiarong, YUAN Shigang, et al. Nuclear track method to measure neutron flux[J]. Chinese Journal of Radiological Health, 2006, 15(2): 6-9(in Chinese).
[16]	曾庆长. 核压力容器辐照脆性破裂问题[J]. 海工科技，1981(3)：76-80.ZENG Qingchang. Radiation brittle fracture of nuclear pressure vessel[J]. Journal of Naval University of Engineering, 1981(3): 76-80(in Chinese).

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文章访问数: 255
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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

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

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