Monte Carlo simulation of neutron sensitivity of microfission chamber in neutron flux measurement

Microfission chambers loaded with highly enriched fissile materials are widely used for measuring power in reactors. The neutron sensitivity of the microfission chamber is a key parameter that determines the accuracy of the power measurement. To evaluate the performance of the FC4A microfission cham...

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Veröffentlicht in:Nuclear science and techniques 2022-06, Vol.33 (6), p.128-138, Article 78
Hauptverfasser: Wu, Ze-Peng, Jiang, Xin-Biao, Zhang, Wen-Shou, Su, Chun-Lei, Zhang-Sun, Yong-Gang, Bao, Li-Hong
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container_end_page 138
container_issue 6
container_start_page 128
container_title Nuclear science and techniques
container_volume 33
creator Wu, Ze-Peng
Jiang, Xin-Biao
Zhang, Wen-Shou
Su, Chun-Lei
Zhang-Sun, Yong-Gang
Bao, Li-Hong
description Microfission chambers loaded with highly enriched fissile materials are widely used for measuring power in reactors. The neutron sensitivity of the microfission chamber is a key parameter that determines the accuracy of the power measurement. To evaluate the performance of the FC4A microfission chamber, in this work, we introduced an accurate and validated model of the microfission chamber, a performed Monte Carlo simulation of the neutron sensitivity of the microfission chamber with GEANT4 code, and conducted an irradiation experiment on the neutron irradiation effect platform #3 of the Xi'an Pulsed Reactor. We compared the simulated sensitivity with the experimental results, which showed that the sensitivity obtained from the simulation was in good agreement with the experimental results. In addition, we studied the impact of the design parameters of the fission chamber on the calculated neutron sensitivity of the microfission chamber.
doi_str_mv 10.1007/s41365-022-01062-6
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subjects Beam Physics
Nuclear Energy
Particle Acceleration and Detection
Particle and Nuclear Physics
Physics
Physics and Astronomy
title Monte Carlo simulation of neutron sensitivity of microfission chamber in neutron flux measurement
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