Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
In this paper, a thermal neutron beam for neutron capture studies at the horizontalneutron channel No.2 of the Dalat Nuclear Research Reactor (DNRR) is designed and simulatedusing the MCNP5 code. The proposal model having a conical collimator of 240.3 cm in length,and neutron filters of Al2O3and B...
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| Những tác giả chính: | , |
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| Định dạng: | Journal article |
| Ngôn ngữ: | English |
| Được phát hành: |
2023
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| Những chủ đề: | |
| Truy cập trực tuyến: | https://scholar.dlu.edu.vn/handle/123456789/3201 https://doi.org/10.15625/0868-3166/17445 https://vjs.ac.vn/index.php/cip/article/view/17445/2543254874 |
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| Thư viện lưu trữ: | Thư viện Trường Đại học Đà Lạt |
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| Tóm tắt: | In this paper, a thermal neutron beam for neutron capture studies at the horizontalneutron channel No.2 of the Dalat Nuclear Research Reactor (DNRR) is designed and simulatedusing the MCNP5 code. The proposal model having a conical collimator of 240.3 cm in length,and neutron filters of Al2O3and Bi crystals with different thicknesses was simulated for optimaladjustment of the filter lengths. The simulation shows that a pure thermal neutron beam canbe obtained at the irradiation position when a composition of crystal filter of 20 cm Al2O3and6 cm Bi crystals are applied into the collimated beam line. The thermal and epithermal neutronfluxes are1.02×108n/cm2/s (accounting for 97.92% of total neutron flux) and0.22×107n/cm2/s(accounting for 2.08% of total neutron flux), respectively |
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