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: Trịnh, Thị Tú Anh, Pham Dang Quyet, Pham Ngoc Son,Phan Bao Quoc Hieu,Nguyen Thi Minh Sang and Cao Dong Vu
Định dạng: Journal article
Ngôn ngữ:English
Được phát hành: 2023
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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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spelling oai:scholar.dlu.edu.vn:123456789-32012023-12-13T04:42:19Z Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor Trịnh, Thị Tú Anh Pham Dang Quyet, Pham Ngoc Son,Phan Bao Quoc Hieu,Nguyen Thi Minh Sang and Cao Dong Vu MCNP simulation; Al2O3crystal; Bi crystal; thermal neutron flux 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 33 2 185-193 Khoa Vật lý và Kỹ thuật hạt nhân 6 Nguyễn Thị Minh Sang X 2023-11-30T02:06:40Z 2023-11-30T02:06:40Z 2023-02-14 Journal article Bài báo đăng trên tạp chí trong nước (có ISSN), bao gồm book chapter 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 en Communications in Physics
institution Thư viện Trường Đại học Đà Lạt
collection Thư viện số
language English
topic MCNP simulation; Al2O3crystal; Bi crystal; thermal neutron flux
spellingShingle MCNP simulation; Al2O3crystal; Bi crystal; thermal neutron flux
Trịnh, Thị Tú Anh
Pham Dang Quyet, Pham Ngoc Son,Phan Bao Quoc Hieu,Nguyen Thi Minh Sang and Cao Dong Vu
Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
description 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
format Journal article
author Trịnh, Thị Tú Anh
Pham Dang Quyet, Pham Ngoc Son,Phan Bao Quoc Hieu,Nguyen Thi Minh Sang and Cao Dong Vu
author_facet Trịnh, Thị Tú Anh
Pham Dang Quyet, Pham Ngoc Son,Phan Bao Quoc Hieu,Nguyen Thi Minh Sang and Cao Dong Vu
author_sort Trịnh, Thị Tú Anh
title Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
title_short Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
title_full Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
title_fullStr Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
title_full_unstemmed Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
title_sort design and simulation of a thermal neutron beam for neutron capture studies at the dalat research reactor
publishDate 2023
url 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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