Chen Li , Ya-Ling Zhang , Zheng Wei , Wei Wang , Xue-Zhi Zhang , Ji-Zheng Duan , Lei Yang
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引用次数: 0
Abstract
The Precision Radiotherapy α-Isotope R&D Platform in Gansu Province aims to produce several alpha emitting isotopes. Due to the bombardment of Th-232 targets with 100 MeV protons, a high-energy n-γ mixed radiation field is generated. Here, we compared the calculated results for calculating the dose attenuation of neutrons in iron and concrete using FLUKA code and the analytical methods in standard DIN 6875-20. We analyzed the impact of carbon content on the shielding capabilities of iron, the results indicate that a small amount of carbon improves the shielding effect, and then compared the effects of different thicknesses of low-carbon steel and heavy concrete composite shielding on forward neutron dose attenuation. Additionally, we calculated and analyzed dose attenuation curves and energy spectra for 1 MeV and 20 MeV neutrons passing through heavy concrete, boron carbide, carbon steel, polyethylene, and borated polyethylene. The shielding capabilities of various materials and their combinations against the n-γ mixed field were compared, and then we optimized the lateral shielding compensation structures based on the results. Finally, we simulated the overall dose distribution of the target station. This study is particularly significant for engineering design of the target stations in the isotope production facilities.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development