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Reference level of the occupational radiation exposure in a deep geological disposal facility for high-level nuclear waste: A Monte Carlo study

机译:深度地质处置设施中高级核废料的职业辐射暴露参考水平:蒙特卡洛研究

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In deep geological repositories for high-level nuclear waste, radiation field around the disposed nuclear waste package is characterized by highly scattered radiations due to the surrounding host rock layers or cement liner. Calculation of the reference level of the occupational radiation exposure in such a facility is hence of interest, since geometrical conditions of the occupational exposure in the facility cannot be readily represented by the standard irradiation geometries considered by ICRP. In this study, a horizontal emplacement drift inside rock salt was modeled to represent a deep geological disposal facility. A nuclear waste package, simulated with a shielding cask loaded with spent nuclear fuel, was placed on the ground of the rock salt drift. A "reference worker" inside the drift was represented by the ICRP/ICRU reference adult voxel phantom. The reference level of the occupational radiation exposure was then calculated with a Monte Carlo code in terms of the effective dose based on the ICRP 2007 recommendation. In order to investigate the occupational exposure of a worker during different working scenarios in the drift, the effective dose was calculated with the voxel phantom placed at various distances and different body orientations with respect to the shielding cask. Furthermore, the effective dose obtained with voxel phantom was compared with that obtained with the fluence-to-effective-dose conversion coefficients for the standard irradiation geometries provided by ICRP. It was found out that (1) usage of the dose conversion coefficients for the isotropic (ISO) geometry, which is recommended by ICRP for highly scattered radiation fields, generally underestimates the effective dose in the rock salt emplacement drift; (2) depending on the orientation of the worker in the drift, the dose conversion coefficients for the anterior-to-posterior (AP) or the rotational (ROT) geometry should be used, in order to obtain an adequate estimation of the effective dose in the rock salt drift. (C) 2017 Elsevier Ltd. All rights reserved.
机译:在用于高级核废料的深层地质处置库中,由于周围的主岩层或水泥衬层,所处置核废料包周围的辐射场的特征是辐射高度分散。因此,在这种设施中计算职业辐射暴露的参考水平非常重要,因为该设施中的职业暴露的几何条件不能通过ICRP所考虑的标准辐射几何图形轻易地表示出来。在这项研究中,对岩盐内部的水平位移进行了建模,以代表深部的地质处置设施。将一个装有废核燃料的屏蔽桶模拟的核废料包放在岩盐漂流的地面上。 ICRP / ICRU参考成人体素体模代表漂流中的“参考工作者”。然后根据ICRP 2007的建议,使用蒙特卡罗代码根据有效剂量计算出职业辐射暴露的参考水平。为了研究工人在漂流中不同工作场景中的职业暴露,计算了有效剂量,将体素体模放置在相对于屏蔽桶的不同距离和不同身体方向上。此外,将体素体模获得的有效剂量与由ICRP提供的标准照射几何结构的通量到有效剂量转换系数获得的剂量进行了比较。结果发现:(1)ICRP推荐的各向同性(ISO)几何形状的剂量转换系数的使用通常会低估岩盐位移漂移中的有效剂量; (2)根据工作人员在漂流中的方位,应使用前后(AP)或旋转(ROT)几何形状的剂量转换系数,以便获得有效剂量的适当估计在盐岩中漂流。 (C)2017 Elsevier Ltd.保留所有权利。

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