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Published: 2018-03-30
Abstract Views: 128
Views PDF: 230
DOI: https://doi.org/10.53747/jnst.v8i1.81
Issue
Vol. 8 No. 1 (2018)
Section
Articles
How to Cite
Trinh Thi , T. A., Nguyen, D. H., Pham, D. Q., & Pham, N. S. (2018). Dose Calculation and Measurement from B¹⁰(n, α)Li⁷ Reaction Using Filtered Neutron Beam at Nuclear Research Institute. Nuclear Science and Technology, 8(1), 29-35. https://doi.org/10.53747/jnst.v8i1.81

Dose Calculation and Measurement from B¹⁰(n, α)Li⁷ Reaction Using Filtered Neutron Beam at Nuclear Research Institute

Trinh Thi Tu Anh1, Nguyen Danh Hung1, Pham Dang Quyet1, Pham Ngoc Son1
1 Dalat University, 01 Phu Dong Thien Vuong Street, Dalat, LamDong, Vietnam

Main Article Content

Abstract

In this research, dose calculation and measurement from B10 (n, α) Li7 reaction using
filtered neutron beam at the Nuclear Research Institute have been reported. Calculation was carried out by Monte Carlo method using MCNP5 code. Neutron activation technique using vanadium foil was employed to determine neutron flux at various positions in phantom from which neutron dose has been calculated using conversion factor. These calculations are basics for the dose determination research of the Boron Neutron Capture Therapy (BNCT) in Vietnam.

Article Details

Keywords

Dose calculation, Monte Carlo, BNCT

References

[1] Y. Nakagawa, “Clinical practice in BNCT to the brain”, IAEA-TECDOC-1223 (2001).
[2] H. Gambarini, S. Agosteo, P. Marchesi, E. Nava, P. Palazzi, A. Pecci, R. Rosa, G. Rosi, R. Tinti, “Three dimensional measurements of absorbed dose in BNCT by Fricke-gel imaging”, IAEA-TECDOC-1223, (2001).
[3] Myong Seop Kim, Sang Jun Park and Byung Jin Jun, “Measurements of In-phantom Neutron Flux Distribution”, Journal of Korean Nuclear Society, 36(3), pp<203-209>, (2004).
[4] Pham Ngoc Son, “Development of filtered neutron beam at Dalat Research Reactor and its application on measurement of nuclear data”, National project’s report, (2012).
[5] ICRU Report 63. Nuclear Data for Neutron and Proton Radiotherapy and for Radiation Protection. International Commission on Radiation Units and Measurements. Bethesda, Maryland, (2000). ISBN 0-913394-62-9.
[6] Kenta Takadaa, Tomonori Isobea , Hiroaki Kumadaa , Tetsuya Yamamotoa, Koichi Shidab, Daisuke Kobayashib, Yutaro Moria, Hideyuki Sakuraia and Takeji Sakaea, “Evaluation of the radiation dose for whole body in boron neutron capture therapy”, Progress in Nuclear Science and Technology, 4, pp<820-823>, (2014).