TY - JOUR AU - Quyet, Pham Dang AU - Son, Pham Ngoc AU - Dien, Nguyen Nhi AU - Son, Nguyen An AU - Anh, Trinh Thi Tu AU - Vu, Cao Dong PY - 2020/12/15 Y2 - 2024/03/28 TI - Simulation of absorbed doses distribution in a polyethylene phantom for BNCT application at the Dalat research reactor JF - Nuclear Science and Technology JA - Nucl. Sci. and Tech. VL - 10 IS - 4 SE - DO - 10.53747/jnst.v10i4.9 UR - http://jnst.vn/index.php/nst/article/view/9 SP - 01-07 AB - <p>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<sup>-6</sup> Gy at the 0.5-cm depth, and reduces to 9.05×10<sup>-7</sup> 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 <sup>1</sup>H(n,γ)<sup>2</sup>H 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<sup>-5</sup> Gy at the 0.5-cm depth, and decreases rapidly to 1.52×10<sup>-5</sup> Gy at the 3-cm position, and mainly depends on the boron and thermal neutron doses caused by the <sup>10</sup>B(n, α)<sup>7</sup>Li and <sup>14</sup>N(n, p)<sup>14</sup>C reactions, respectively.</p> ER -