Jazbec Anže, Kos Bor, Ambrožič Klemen, Snoj Luka
University of Ljubljana, Faculty of Mathematics and Physics, Slovenia; Jožef Stefan Institute, Ljubljana, Slovenia.
Jožef Stefan Institute, Ljubljana, Slovenia.
Appl Radiat Isot. 2021 Feb;168:109510. doi: 10.1016/j.apradiso.2020.109510. Epub 2020 Nov 17.
Monte Carlo N-Particle (MCNP) transport code accelerated by AutomateD VAriaNce reducTion Generator (ADVANTG) code was used to simulate neutron and prompt gamma particles emitted from TRIGA research reactor during operation. Firstly, the method was validated by measuring dose rates around open beam port number 5 was unplugged. Neutron and gamma dose rates inside the reactor hall in the vicinity of the beam port were calculated and compared to the measurements. Due to the satisfactory agreement, the method was later used to design external shielding for the same beam port when it was upgraded - special mechanism was installed that allows irradiation of larger samples. Computational analysis of the proposed shielding configuration provided acceptable dose rate levels inside the reactor hall. When the shield was constructed, calculated dose rates were confirmed by the actual measurements. No modifications were needed.
利用由自动方差缩减生成器（ADVANTG）代码加速的蒙特卡罗N粒子（MCNP）输运代码，模拟了TRIGA研究堆运行期间发射的中子和瞬发伽马粒子。首先，通过测量5号开放束流端口未堵塞时周围的剂量率对该方法进行了验证。计算了束流端口附近反应堆大厅内的中子和伽马剂量率，并与测量值进行了比较。由于一致性良好，该方法后来被用于在同一束流端口升级时设计外部屏蔽——安装了特殊机构以允许照射更大的样品。对 proposed shielding configuration 的计算分析在反应堆大厅内提供了可接受的剂量率水平。当屏蔽建造完成后，计算出的剂量率通过实际测量得到了证实，无需进行修改。 （注：原文中“proposed shielding configuration”未翻译完整，可能是输入有误，你可根据实际情况修正后再让我翻译）
