Reactor Thermal Neutron Spectrum Measurement with Time of Flight Method

Author:

Liu Shu Huan1,Jiang Xin Biao2,Zhang Wen Shou2,Yu Qing Yu2,Zhong Yun Hong2,Yang Jun2,Zhu Guang Ning2,Wang Kai2,Chen Da2

Affiliation:

1. Xi’an Jiaotong University

2. Northwest Institute of Nuclear Technology

Abstract

The basic principle of neutron spectrum measured with time of flight method was simply introduced. The design of the experimental system for the time of flight spectrum detected in the thermal column of the reactor was offered. The most probable neutron energy of the measured thermal neutron was about 0.0248±0.0007eV, and the spectrum average energy was 0.042±0.001eV. The results showed that the measured spectrum was softer than thermal Maxwellian theory spectrum.

Publisher

Trans Tech Publications, Ltd.

Reference5 articles.

1. C.F. COOK. A fast neutron time-of-flight spectrometer. Nuclear Instrument and methods. 15(1962), pp.137-145.

2. Nuclear Physics Experiment Techniques(the second volume). Compiled by FuDan university, Tsinghua University and Peking University. Atomic Energy Press(1982). Bejing, p.26~31.

3. Yue Qian. Thermal neutron fluence rate absolute measurement with 235U fission chamber, (Master thesis). Atomic Energy Institute. 1984, p.14.

4. Chen Minheng, Cong Dezi Fang Tunan. Principle of chemical engineering. Beijing, Chemical industry press(1997). p.213.

5. S. Berg and W. N. Mce. Groy. A Computer-Automated Iterative Method for Neutron Flux Spectra Determination by Foil Activation. Atomic International. Tech. Rep. No. AFWL-TR-67-41, Sept. (1967).

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