Courtney J C, Klann R T
Nuclear Science Center, Louisiana State University, Baton Rouge 70803-5820, USA.
Health Phys. 1997 Jan;72(1):120-7. doi: 10.1097/00004032-199701000-00017.
Testing has been completed for two lightly shielded areas that support operations in the Fuel Conditioning Facility at the Argonne National Laboratory site at the Idaho National Engineering Laboratory. Operational requirements dictated the use of a radiography source containing 0.44 TBq (12 Ci) of 192Ir to challenge reinforced concrete and steel shields that surround a decontamination, maintenance, and repair area for contaminated equipment used in hot cell operations. A more intense source containing 0.89 TBq (24 Ci) of 192Ir was used to test lead shot and steel shields around tanks in a radioactive liquid waste system and the boundaries of the room that contained it. Measurement procedures were developed to find design flaws and construction deficiencies while minimizing radiation exposure to test participants. While the shields are adequate to limit gamma ray deep dose equivalents to 10 mSv y(-1) (1 rem y(-1)) or less to facility personnel, several modifications were necessary to assure that the attenuation is adequate to keep dose rates less than 5 microSv h(-1) (0.5 mrem h(-1)) in normally occupied areas.
在爱达荷国家工程实验室的阿贡国家实验室场址，对燃料处理设施中两个轻屏蔽区域的测试已经完成，这两个区域用于支持相关作业。运行要求规定使用一个含有0.44太贝克勒尔（12居里）铱 - 192的射线照相源，以检测围绕热室作业中受污染设备的去污、维护和修理区域的钢筋混凝土和钢屏蔽层。一个含有0.89太贝克勒尔（24居里）铱 - 192的更强源被用于测试放射性液体废物系统中储罐周围的铅丸和钢屏蔽层以及容纳该系统的房间边界。制定了测量程序，以发现设计缺陷和施工不足，同时尽量减少测试参与者所受的辐射暴露。虽然这些屏蔽层足以将设施人员所受的伽马射线深部剂量当量限制在每年10毫希沃特（1雷姆/年）或更低，但仍需进行一些改进，以确保衰减足够大，使正常占用区域的剂量率保持在每小时5微希沃特（0.5毫雷姆/小时）以下。
