Calculation of thermal neutron scattering data of MgF2 and its effect on beam shaping assembly for BNCT

Jiaqi Hu; Zhaopeng Qiao; Lunhe Fan; Yongqiang Tang; Liangzhi Cao; Tiejun Zu; Qingming He; Zhifeng Li; Sheng Wang

Nuclear Engineering and Technology (Apr 2023)

Calculation of thermal neutron scattering data of MgF2 and its effect on beam shaping assembly for BNCT

Jiaqi Hu,
Zhaopeng Qiao,
Lunhe Fan,
Yongqiang Tang,
Liangzhi Cao,
Tiejun Zu,
Qingming He,
Zhifeng Li,
Sheng Wang

Affiliations

Jiaqi Hu: School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
Zhaopeng Qiao: School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
Lunhe Fan: School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
Yongqiang Tang: School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
Liangzhi Cao: School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
Tiejun Zu: School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
Qingming He: School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China
Zhifeng Li: School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China; Corresponding author.
Sheng Wang: School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China; State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China; Corresponding author. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China.

Journal volume & issue: Vol. 55, no. 4
pp. 1280 – 1286

Abstract

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MgF2 as a moderator material has been extensively used in the beam shaping assembly (BSA) that plays an important role in the boron neutron capture therapy (BNCT). Regarded as important for applications, the thermal neutron scattering data of MgF2 were calculated, based on the phonon expansion model. The structural properties of MgF2 were researched by the VASP code based on the ab-initio methods. The PHONOPY code was employed to calculate the phonon density of states. Furthermore, the NJOY code was used to calculate the thermal neutron scattering data of MgF2. The calculated inelastic cross sections plus absorption cross sections are in agreement with the available experimental data. The neutron transport in the BSA has been simulated by using a hybrid Monte-Carlo-Deterministic code NECP-MCX. The results indicated that compared with the calculation of the free gas model, the thermal neutron flux and epithermal neutron flux at the BSA exit port calculated by using the thermal neutron scattering data of MgF2 were reduced by 27.7% and 8.2%, respectively.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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