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Study on the radiation device of 241Am-Be neutron source and its dosimetric properties |
TANG Xiaohao1, HONG Bo2, FAN Shengnan3, CAO Lei4, LAN Changlin2, PAN Xiaodong2 |
1. Editorial Department of 《Atomic Energy Science and Technology》, China Institute of Atomic Energy, Beijing 102413 China; 2. School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000 China; 3. National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention, Beijing 100088 China; 4. The Beijing Prevention and Treatment Hospital of Occupational Disease for Chemical Industry, Beijing 100089 China |
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Abstract Objective To design and build a set of experimental equipment for neutron radiation irradiation by using the 241Am-Be neutron source.Methods In the preliminary work, the spatial distribution data of the neutron energy spectrum and the gamma energy spectrum inside and outside the device were simulated by Monte Carlo method, and the changes of radiation fluence rate with spatial distribution was studied. The model of the 241Am-Be neutron device was established, and the neutron transport process in the irradiation field was studied using the method of shadow cone, inverse square law and other data analysis methods.Results Based on the simulation results, the normalized effective does of fast neutron fluence at the measurement point is about 72.9 pSv/n, and the one of photon fluence is about 3.04 pSv/γ. The ratio of effective dose of photon fluence to neuteon is about 4.17%.Conclusion Using Monte Carlo method, a standard model of 241Am-Be neutron source was constructed, the shadow cone design was optimized, and the feasibility of using the shadow cone conversion method to establish a standard neutron source radiation device was discussed.
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Received: 11 September 2020
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