Reactor Thermal Neutron Spectrum Measurement with Time of Flight Method

Shu Huan Liu; Xin Biao Jiang; Wen Shou Zhang; Qing Yu Yu; Yun Hong Zhong; Jun Yang; Guang Ning Zhu; Kai Wang; Da Chen

doi:10.4028/www.scientific.net/AMM.738-739.899

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HomeApplied Mechanics and MaterialsApplied Mechanics and Materials Vols. 738-739Reactor Thermal Neutron Spectrum Measurement with...

Reactor Thermal Neutron Spectrum Measurement with Time of Flight Method

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.

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Periodical:

Applied Mechanics and Materials (Volumes 738-739)

Pages:

899-903

DOI:

https://doi.org/10.4028/www.scientific.net/AMM.738-739.899

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Online since:

March 2015

Authors:

Shu Huan Liu*, Xin Biao Jiang, Wen Shou Zhang, Qing Yu Yu, Yun Hong Zhong, Jun Yang, Guang Ning Zhu, Kai Wang, Da Chen

Keywords:

Reactor, Thermal Neutron Spectrum, Time of Flight Method (TOF)

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References

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

DOI: 10.1016/0029-554x(62)90063-0

Google Scholar

[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.

Google Scholar

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

Google Scholar

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

Google Scholar

[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).

Google Scholar