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首页> 外文期刊>Radiation measurements >Assessment of fast and thermal neutron ambient dose equivalents around the KFUPM neutron source storage area using nuclear track detectors
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Assessment of fast and thermal neutron ambient dose equivalents around the KFUPM neutron source storage area using nuclear track detectors

机译：使用核径迹探测器评估KFUPM中子源存储区域附近的快速和热中子环境剂量当量

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A set of five Am-241-Be neutron sources are utilized in research and teaching at King Fahd University of Petroleum and Minerals (KFUPM). Three of these sources have an activity of 16 Ci each and the other two are of 5 Ci each. A well-shielded storage area was designed for these sources. The aim of the study is to check the effectiveness of shielding of the KFUPM neutron source storage area. Poly allyl diglycol carbonate (PADC) Nuclear track detectors (NTDs) based fast and thermal neutron area passive dosimeters have been utilized side by side for 33 days to assess accumulated low ambient dose equivalents of fast and thermal neutrons at 30 different locations around the source storage area and adjacent rooms. Fast neutron measurements have been carried out using bare NTDs, which register fast neutrons through recoils of protons, in the detector material. NTDs were mounted with lithium tetra borate (Li2B4O7) converters on their surfaces for thermal neutron detection via B-10 (n, alpha)Li-6 and Li-6(n, alpha)H-3 nuclear reactions. The calibration factors of NTD both for fast and thermal neutron area passive dosimeters were determined using thermoluminescent dosimeters (TLD) with and without a polyethylene moderator. The calibration factors for fast and thermal neutron area passive dosimeters were found to be 1.33 proton tracks cm(-2) mu Sv(-1) and 31.5 alpha tracks cm(-2) mu Sv(-1), respectively. The results show variations of accumulated dose with the locations around the storage area. The fast neutron dose equivalents rates varied from as low as 182 mu Sv h(-1) up to 10.4 mu Sv h(-1) whereas those for thermal neutron ranged from as low as 7 nSv h(-1) up to 9.3 mu Sv h(-1). The study indicates that the area passive neutron dosimeter was able to detect dose rates as low as 7 and 182 nSvh(-1) from accumulated dose for thermal and fast neutrons, respectively, which were not possible to detect with the available active neutron dosimeters. (c) 2005 Elsevier Ltd. All rights reserved.
机译：法赫德国王石油和矿产大学（KFUPM）在研究和教学中利用了五个Am-241-Be中子源。这些源中的三个的活度分别为16 Ci，其他两个的活度均为5 Ci。为这些源设计了一个良好屏蔽的存储区。这项研究的目的是检查KFUPM中子源存储区的屏蔽效果。并排利用基于聚烯丙基碳酸二乙二醇酯（PADC）的核径迹检测器（NTDs）的快速和热中子区域被动剂量计33天，以评估源存储周围30个不同位置的快速和热中子的累积低环境剂量当量区域和相邻房间。快速中子测量是使用裸露的NTD进行的，裸露的NTD通过质子反冲在探测器材料中记录快速中子。 NTD在其表面装有四硼酸锂（Li2B4O7）转换器，用于通过B-10（n，α）Li-6和Li-6（n，α）H-3核反应进行热中子检测。使用带和不带聚乙烯慢化剂的热发光剂量计（TLD）确定快速和热中子面积被动剂量计的NTD校准因子。快速和热中子面积被动剂量计的校准系数分别为1.33质子径cm（-2）μSv（-1）和31.5α径cm（-2）μSv（-1）。结果显示累积剂量随存储区域周围位置的变化。快速中子剂量当量率的范围从低至182 mu Sv h（-1）到10.4 mu Sv h（-1），而热中子的剂量当量率从低至7 nSv h（-1）到9.3 mu Sv h（-1）。研究表明，该区域无源中子剂量计能够从热中子和快中子的累积剂量中分别检测出低至7和182 nSvh（-1）的剂量率，而现有的有源中子剂量计则无法检测到该剂量率。 （c）2005 Elsevier Ltd.保留所有权利。

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