西安脉冲堆热柱孔道中子束流参数测量

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Parameter Measurement of Thermal Neutron Beam in Thermal Column of Xi’an Pulse Reactor

1. Northwest Institute of Nuclear Technology, Xi'an, 710613, China;
2. Department of Engineering Physics, Tsinghua University, Beijing, 100084, China

摘要: 采用飞行时间法测量了西安脉冲堆热柱孔道热中子束流中子能谱分布,能谱测量结果较Thermal Maxwellian理论谱偏软,中子谱平均能量为0.042±0.01eV。采用金箔活化法测得热柱孔道出口前端热中子注量率为1.18×10⁵cm^-2.s^-1,热中子注量率测量的不确定度为3%。
- 热中子能谱 /
- 热中子注量率 /
- 反应堆 /
- 飞行时间法 /
- 活化法
Abstract: The distribution of the neutron spectra in the thermal column of Xi’an pulse reactor was measured with the time of flight method in this paper.Comparing with the thermal Maxwellian theory neutron spectra,the thermal neutron spectra measured in experiment is a little softer,and the average neutron energy in measurement spectra is about 0.042±0.01eV.The thermal neutron fluence rate at the front end of the thermal column,preliminarily measured with gold foil activation techniques,is about 1.18×10⁵cm^-2.s^-1.The standard uncertainty of the measured thermal neutron fluence is about 3%.
- Thermal neutron spectra /
- Thermal neutron fluence rate /
- Reactor /
- Time of flight method /
- Activation method