Research on Measurement of Neutron Flux in Irradiation Channels of Research Reactor

Yin Zhitao; L&#220; Zheng; Wang Yulin; Zheng Wuqin

Feb. 2025

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Yin Zhitao, LÜ Zheng, Wang Yulin, Zheng Wuqin. Research on Measurement of Neutron Flux in Irradiation Channels of Research Reactor[J]. Nuclear Power Engineering, 2014, 35(1): 117-121.

Citation:

Yin Zhitao, LÜ Zheng, Wang Yulin, Zheng Wuqin. Research on Measurement of Neutron Flux in Irradiation Channels of Research Reactor[J]. Nuclear Power Engineering, 2014, 35(1): 117-121.

Yin Zhitao, LÜ Zheng, Wang Yulin, Zheng Wuqin. Research on Measurement of Neutron Flux in Irradiation Channels of Research Reactor[J]. Nuclear Power Engineering, 2014, 35(1): 117-121.

Citation:

Yin Zhitao, LÜ Zheng, Wang Yulin, Zheng Wuqin. Research on Measurement of Neutron Flux in Irradiation Channels of Research Reactor[J]. Nuclear Power Engineering, 2014, 35(1): 117-121.

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Research on Measurement of Neutron Flux in Irradiation Channels of Research Reactor

1. State Nuclear Power Technology Research and Development Center, Beijing, 100190, China;
2. China Institute Of Atomic Energy, Beijing, 102413, China

Received Date: 2012-11-13
Rev Recd Date: 2013-11-21

Available Online: 2025-02-15

Abstract

Abstract

Relative distribution of thermal neutron flux in the irradiation channel is measured by classical activation foil method. After that, on a representative point in the irradiation channel, neutron temperature and absolute neutron flux are also measured. Cadmium ratio correction method is used to check the experiment result in the end. Comparative analysis shows that the results from two different methods are agreed pretty well, which adds the credibility of experiment results.
- Thermal neutron flux,
- Neutron temperature,
- Relative distribution,
- Activation foil method,
- Cadmium ratio correction method