GUO Guangshui, male, born in 1982, graduated from University of South China with a master’s degree in 2008, focusing on application of nuclear technology
GUO Guangshui,ZHANG Long,MENG Xianfang,et al.Simulated analysis of the influence factor of the neutron response in neutron shielding testing system[J].NUCLEAR TECHNIQUES,2019,42(09):60-66.
GUO Guangshui,ZHANG Long,MENG Xianfang,et al.Simulated analysis of the influence factor of the neutron response in neutron shielding testing system[J].NUCLEAR TECHNIQUES,2019,42(09):60-66. DOI: 10.11889/j.0253-3219.2019.hjs.42.090503.
Simulated analysis of the influence factor of the neutron response in neutron shielding testing system
Shielding materials has been widely used in nuclear field
but no uniform standards have been established so far for the neutron shielding performance test of shielding materials.
Purpose
2
This study aims to analyze the factors affecting the reliability and stability of neutron response in neutron shielding test system.
Method
2
The SuperMC program was employed to simulate the neutron shielding test system modeling
and the influence factors such as the distance of test sample to the detector
the axis deviation of test sample to the detector
the axis deviation of the radiation source to the detector and the size of test sample. Simulation data of neutron flux
neutron mean energy and neutron energy spectrum were compared and analyzed with the neutron response curve of neutron detection instrument.
Results
2
Analysis results show that the detector and radiator adjusted to the center line position of the collimation area achieve stable and reliable performance. The distance between the detector and the radiator in the range of 130~180 cm
and sample size greater than 30 cm are recommended.
Conclusion
2
This paper provides reasonable and reliable test parameters for the neutron shielding test system
and theoretical basis for reducing the test error of the test system and improving reliability of test data.
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Full reactor core calculation performance validation of SuperMC based on Hoogenboom benchmark
Parallel computing method of Monte Carlo criticality calculation based on bi-directional traversal
Development of the neutronics calculation module of neutronics and thermal hydraulic calculation program NECP-Panda for pebble-bed high temperature gas-cooled reactor
Development and validation of LightAB: a new light general-purpose activation-burnup program
Calculation methods of parameters in α particle measurement
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