Journal
APPLIED RADIATION AND ISOTOPES
Volume 135, Issue -, Pages 147-154Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.apradiso.2018.01.021
Keywords
Neutron; Shielding; Optimization; Compact; Lightweight; Low activation
Categories
Funding
- Key Natural Science fund of the Shaanxi Province of China [2015JZ001]
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To minimize the size and weight of a vehicle-mounted accelerator-driven D-T neutron source and protect workers from unnecessary irradiation after the equipment shutdown, a method to optimize radiation shielding material aiming at compactness, lightweight, and low activation for the fast neutrons was developed. The method employed genetic algorithm, combining MCNP and ORIGEN codes. A series of composite shielding material samples were obtained by the method step by step. The volume and weight needed to build a shield (assumed as a coaxial tapered cylinder) were adopted to compare the performance of the materials visually and conveniently. The results showed that the optimized materials have excellent performance in comparison with the conventional materials. The MCNP6-ACT method and the rigorous two steps (R2S) method were used to verify the activation grade of the shield irradiated by D-T neutrons. The types of radionuclide, the energy spectrum of corresponding decay gamma source, and the variation in decay gamma dose rate were also computed.
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