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Measurement and analysis of the 232Th(n, 2n) reaction rate in a polyethylene shell with DT neutrons
- NUCLEAR TECHNIQUES Vol. 41, Issue 6, Article number: 060502(2018)
- 作者机构：
1.中国工程物理研究院 核物理与化学研究所 绵阳 621900
2.四川大学 物理科学与技术学院 核工程与核技术系 成都 610064
3.清华大学 工程物理系 北京 100084
- 作者简介：
- 基金信息：National Natural Science Foundation of China;Presidential Foundation of China Academy of Engineering Physics;Neutron Key Laboratory Foundation
DOI：10.11889/j.0253-3219.2018.hjs.41.060502
CLC： TL99Received：05 February 2018，
Revised：14 March 2018，
Published：10 June 2018
- 稿件说明：
移动端阅览
Zhujun LIU, Yiwei YANG, Lei ZHENG, et al. Measurement and analysis of the 232Th(n, 2n) reaction rate in a polyethylene shell with DT neutrons[J]. Nuclear techniques, 2018, 41(6): 060502
Zhujun LIU, Yiwei YANG, Lei ZHENG, et al. Measurement and analysis of the 232Th(n, 2n) reaction rate in a polyethylene shell with DT neutrons[J]. Nuclear techniques, 2018, 41(6): 060502 DOI： 10.11889/j.0253-3219.2018.hjs.41.060502.
摘要
232
Th（n，2n）数据对于钍基反应堆研究十分重要，有必要针对其开展中子积分实验，因此，建立了聚乙烯球基准宏观装置，利用活化法在DT中子源下开展了测量
232
Th（n，2n）反应率的中子积分实验。实验中分别采用了钍粉末以及钍片两种样品形态，以消除实验样品状态对实验结果的影响，将样品置于与D离子入射方向成0°的位置进行辐照，利用金硅面α探测器进行中子产额监测以及中子注量波动监测。辐照结束后，利用高纯锗谱仪离线测量反应产物
231
Th发射的能量为84.2 keV的γ射线，得到
232
Th（n，2n）反应率值。同时使用MCNP（Monte Carlo N Particle Transport Code）在数据库ENDF/B-.1 Ⅶ、ENDF/B-.0 Ⅶ、JENDL4.0下对实验进行了精确模拟，数据库JENDL4.0下的反应率计算结果与实验符合较好。
Abstract
Background
2
The
232
Th(n
2n) reaction dominates the neutron generation
so the validity of the cross section data is significant in the thorium based reactor.
Purpose
2
In order to provide the data reference for the design of thorium based reactor
an integral experiment to measure the
232
Th(n
2n) reaction rate was carried out using the activation method in a polyethylene shell with DT neutrons.
Methods
2
In the experiment
thorium samples were arranged in the 0° direction to the incident D
+
beam
and a Au-Si surface barrier detector was used to monitor the neutron yield and the fluctuation of neutron flux.
Results
2
After irradiation
the 84.2 keV γ ray emitted from
231
Th was measured by HPGe spectrometer
and the
232
Th(n
2n) reaction rate was then obtained. The thorium sample was in foil and powder respectively to eliminate the effect of the sample condition. Simultaneously
the experiment was simulated precisely using Monte Carlo N Particle Transport Code (MCNP) code in the ENDF/B-Ⅶ.1
ENDF/B-Ⅶ.0
and JENDL4.0 libraries.
Conclusion
2
The calculated values in the JENDL4.0 were in good agreement with the experimental ones
which can provide reference for the design of thorium based reactors.
关键词
Keywords
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