DIII-D辐射屏蔽程序和经验

P. Taylor
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引用次数: 2

摘要

DIII-D托卡马克采用中子辐射屏蔽,可以增强等离子体操作,增加中子产量,同时最小化现场边界剂量水平。中子率高达4*10/sup 15/中子/秒,总中子产量高达4*10/sup 15/中子/秒,同时保持现场剂量低于美国能源部每年20 mrem的管理水平。辐射屏蔽比预屏蔽值提高了300倍,与设计计算相符。自安装防护罩以来,场地的最大中子剂量每次少于0.03雷姆,每天少于0.4雷姆。在操作过程中,现场中子和伽马剂量由基于pc的计算机系统连续监测,该系统提供了测量射击期间发生的低剂量水平的方法,包括射击后的背景减法。中子和伽马剂量被测量,并按剂量、小时和天在数据库中存档。在运行日之后和船舶进入期间,监测机器的激活情况,并确定激活的核素。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
DIII-D radiation shielding procedures and experiences
The DIII-D tokamak operates with a neutron radiation shield to allow enhanced plasma operations with increased neutron production while minimizing the site boundary dose level. Neutron rates as high as 4*10/sup 15/ neutron/s and total neutron production as high as 4*10/sup 15/ neutrons per shot are obtained while maintaining the site dose below the DOE (Department of Energy) administrative level of 20 mrem per year. The radiation shielding has increased by a factor of 300 over the preshield value and is in agreement with the design calculation. The maximum site neutron dose since installation of the shield has been less than 0.03 mrem for a shot and less than 0.4 mrem for a day. The site neutron and gamma dose are monitored continuously during operations by a PC-based computer system that provides the means of measuring the low dose levels that occur during a shot by including postshot background subtraction. The neutron and gamma dose are measured and archived by shot, hour, and day in a database. Activation of the machine after a run day and during vessel entries is monitored, and the activated nuclides have been determined.<>
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