Simulation of absorbed doses distribution in a polyethylene phantom for BNCT application at the Dalat research reactor

Pham Dang Quyet1, Pham Ngoc Son2, Nguyen Nhi Dien2, Nguyen An Son1, Trinh Thi Tu Anh1, Cao Dong Vu2
1 The University of Dalat, 01 Phu Dong Thien Vuong Street, Dalat, Lamdong
2 Nuclear Research Institute, 01 Nguyen Tu Luc Street, Dalat, Lamdong

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In this paper, the distribution of absorbed dose components in a polyethylene phantom for BNCT application at Dalat Nuclear Research Reactor (DNRR) were calculated using the MCNP5 code. The configuration of horizontal neutron channel No.2 of the DNRR, which contains a cylindrical collimator with neutron filters of 20-cm Si and 3-cm Bi, was simulated. The results show that the gamma dose along the central axis of the phantom has the maximum value of 1.82×10-6 Gy at the 0.5-cm depth, and reduces to 9.05×10-7 Gy at the 3-cm depth. The main contribution to gamma dose is due to the interaction of thermal neutron with hydrogen in the phantom via the 1H(n,γ)2H reaction, and its value is much smaller than thermal neutron dose. The total absorbed dose along the central axis of the phantom has the maximum value of 7.87×10-5 Gy at the 0.5-cm depth, and decreases rapidly to 1.52×10-5 Gy at the 3-cm position, and mainly depends on the boron and thermal neutron doses caused by the 10B(n, α)7Li and 14N(n, p)14C reactions, respectively.

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