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The Implementation of Radiological Characterization for Reactor Decommissioning

The Implementation of Radiological Characterization for Reactor Decommissioning
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摘要 The radiological characterization is to determine the type, the distribution and the radioactivity of the radionuclide in the reactor by investigation of the information, instrumentation detection, sampling analyses and theoretical calculation. It is used for determination of the decommissioning implementation option and radiological protection measure of the workers. After completion of the decommissioning it is used for determination of the site release. The radiological characterization should go through whole decommissioning process, which includes: the collection and review of historical file, the performing calculation of radionuclide inventory in the reactor, in situ measurement, sampling analyses, the review and evaluation of the data obtained and the comparison of calculated result with measured date etc.. The special attention should be paid to the radiological characterization information from the key part of reactor in decommissioning end state. The sampling from the "hot spot" should not be lost; the number of the sampling should be reasonable based on reliable statistics. The radioactivity density for site release should comply with the guide, standard and regulation of International Atomic Energy Agency and China.
出处 《Journal of Energy and Power Engineering》 2011年第11期1109-1112,共4页 能源与动力工程(美国大卫英文)
关键词 Reactor decommissioning radiological characterization hot spot. 反应堆退役 辐射特性 放射性核素 国际原子能机构 计算结果 采样分析 网站发布 现场测量
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参考文献4

  • 1IAEA, Monitoring for compliance with criteria for unrestricted release related to decommissioning of nuclear facilities, Technical Reports Series No. 334, Vienna, 1992.
  • 2IAEA, Radiological characterization of shut down nuclear reactor for decommissioning purposes, Technical Report Series No. 389, Vienna, 1998.
  • 3IAEA, Applications of the concepts of exclusion, exemption and clearance, Safety Standard Series No. RS-G-1.7, Vienna, 2004.
  • 4IAEA, Release of sites from regulatory control on termination of practice, Safety Standard Series No, WS-G-5.1, Vienna, 2006.

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