Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor

Author affiliations

Authors

  • Trinh Thi Tu Anh The University of Dalat, 01 Phu Dong Thien Vuong, Dalat, Lam Dong, Vietnam
  • Pham Dang Quyet The University of Dalat, 01 Phu Dong Thien Vuong, Dalat, Lam Dong, Vietnam https://orcid.org/0000-0002-8984-7747
  • Pham Ngoc Son Nuclear Research Institute, 01 Nguyen Tu Luc, Dalat, Lam Dong, Vietnam https://orcid.org/0000-0002-4489-9957
  • Phan Bao Quoc Hieu Nuclear Research Institute, 01 Nguyen Tu Luc, Dalat, Lam Dong, Vietnam https://orcid.org/0000-0001-9279-0027
  • Nguyen Thi Minh Sang The University of Dalat, 01 Phu Dong Thien Vuong, Dalat, Lam Dong, Vietnam
  • Cao Dong Vu Nuclear Research Institute, 01 Nguyen Tu Luc, Dalat, Lam Dong, Vietnam https://orcid.org/0000-0002-6486-1059

DOI:

https://doi.org/10.15625/0868-3166/17445

Keywords:

MCNP, design, crystal Al2O3, sapphire, thermal neutron flux

Abstract

This paper presents the application of the MCNP5 code to conduct a modification design and simulation of a thermal neutron beam for neutron capture studies at the Dalat Nuclear Research Reactor (DNRR). The designed configuration of the horizontal neutron channel No.2 at the DNRR, which contains a conical collimator of 240.3 cm in length, and neutron filters of crystal Al2O3 and Bi with alternative thickness, were simulated. A pure thermal neutron beam can be obtained at the irradiation position when a composition of crystal filter of 20 cm Al2O3 and 6 cm Bi is employed. The thermal and epithermal neutron fluxes are 1.02´108 n/cm2/s (account for 97.92% of total neutron flux) and 0.22´107 n/cm2/s (account for 2.08% of total neutron flux), respectively.

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References

T. Matsumoto, Design of neutron beams for boron neutron capture therapy for Triga reactor, Journal of Nuclear Science and Technology, vol. 33, pp. 171-178, 1996. doi:10.1080/18811248.1996.9731881. DOI: https://doi.org/10.1080/18811248.1996.9731881

M. Monshizadeh, Y. Kasesaz, H. Khalafi, and S. Hamidi, MCNP design of thermal and epithermal neutron beam for BNCT at the Isfahan MNSR, Progress in Nuclear Energy, vol. 83, pp. (2015), 427-432. doi:10.1016/j.pnucene.2015.05.004. DOI: https://doi.org/10.1016/j.pnucene.2015.05.004

Pham Dang Quyet, Pham Ngoc Son, Nguyen Nhi Dien, Trinh Thi Tu Anh, and Cao Dong Vu, Simulation design of thermal neutron collimators for neutron capture studies at the Dalat Research Reactor, Asian Journal of Scientific Research, vol. 13, (2020), 214-218. doi:10.3923/ajsr.2020.214.218. DOI: https://doi.org/10.3923/ajsr.2020.214.218

K. Myong-Seop, L. Byung-Chul, H. Sung-Yul, et al., Development and characteristics of the HANARO neutron irradiation facility for applications in the boron neutron capture therapy field, Phys. Med. Biol., vol. 52, (2007), 2553-2566. doi:10.1088/0031-9155/52/9/015. DOI: https://doi.org/10.1088/0031-9155/52/9/015

K. Mishra, A. I. Hawari, and V. H. Gillette, Design and performance of a thermal neutron imaging facility at the North Carolina State University PULSTAR reactor, IEEE transactions on nuclear science, vol. 56, (2006), 3904-3911. doi:10.1109/tns.2006.884323. DOI: https://doi.org/10.1109/TNS.2006.884323

Nguyen Nhi Dien et al., Utilisation of the Dalat Research Reactor after its core conversion, in Joint IGORR 2014/ IAEA Technical Meeting, Bariloche, Argentina, 2014.

Pham Ngoc Son, Vuong Huu Tan, Nguyen Nhi Dien, Nguyen Xuan Hai, Tran Tuan Anh, Ho Huu Thang, and Cao Dong Vu, Development of thermal filtered neutron beam based on the radial channel No. 2 of Dalat research reactor, Science and Technics Publishing House, pp. 21-27, 2010.

Y. Kasesaz, E. Bavarnegin, M. Golshanian, et al., BNCT project at Tehran Research Reactor: current and prospective plans, Progress in Nuclear Energy, vol. 91, (2016), 107-115. doi:10.1016/j.pnucene.2016.04.010. DOI: https://doi.org/10.1016/j.pnucene.2016.04.010

M. Adib, Cross-Section of Single-Crystal Materials used as Thermal Neutron Filters, in VII Radiation Physics & Protection Conference, Ismailia-Egypt, 27-30 November 2004.

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Published

23-04-2023

How to Cite

[1]
A. Trinh Thi Tu, Q. Pham Dang, S. Pham Ngoc, H. Phan Bao Quoc, S. Nguyen Thi Minh, and V. Cao Dong, “Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor”, Comm. Phys., vol. 33, no. 2, p. 185, Apr. 2023.

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Section

Papers
Received 22-08-2022
Accepted 14-02-2023
Published 23-04-2023