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一种针对多机组事故的操作干预水平应急决策辅助系统 被引量:1

A decision support system based on OILs optimized for multi-unit accident
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摘要 操作干预水平(OIL)是指对应于某一特定公众防护行动通用干预水平的易于测量的辐射量,用于在核事故期间直接与监测结果比较给出应急防护行动建议。福岛核事故后,我国核应急准备和响应向着多机组方向发展,本研究提出了一种针对多机组事故优化的OIL应急决策辅助系统,将每个机组发生的事故后果进行单独计算和评价,最后将它们对环境辐射后果的贡献进行迭加并代入原先计算公式中,即得到多机组事故下的OIL值。在优化方法的基础上,系统实现了单机组和多机组事故情景下的OIL查询、计算、修正以及后续的应急辅助决策功能。目前,该系统已应用于秦山、田湾、宁德、阳江等核电基地,其模式和功能在实际应用中得到了不断验证和完善,为核事故应急提供了重要的辅助决策手段和工具。 OILs are measurable radiation parameters which are related to the generic intervention level of the specific action for public protection. OILs can be used to provide recommendations on emergency protective actions through comparison with environmental monitoring data. After Fukushima nuclear accident, emergency preparedness and response of nuclear power plants in China focuses on the issues of multi-unit accident. Based on the methods of calculation and revision of OILs suggested by IAEA, methods of calculation OILs for multi- unit accident were established, and the corresponding decision support system was also designed and implemented. The system provided a complete process for use of OILs including the function of data management, data query, calculation, revision and decision on protective actions, which can be used for both single-reactor and multi-reactor accident. The system has been applied in Qinshan, Ningde, Sanmen, Taishan and Yangjiang NPPs in China.
作者 陈谦 黄义超 陶乃贵 孙雪峰 刘占阳 CHEN Qian;HUANG Yichao;TAO Naigui;SUN Xuefeng;LIU Zhanyang(Suzhou Nuclear Power Research Institute Co.Ltd.,Jiangsu Suzhou 215004)
出处 《辐射防护》 CAS CSCD 北大核心 2018年第5期389-395,共7页 Radiation Protection
关键词 操作干预水平 防护行动 决策支持系统 轻水堆 多机组事故 OIL protective action decision support system light water reactor multi-unit accident
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  • 1凌永生,施仲齐,王醒宇.IAEA推荐的操作干预水平OIL1和OIL2缺省值的导出及其适宜性的初步研究[J].辐射防护,2005,25(1):11-17. 被引量:7
  • 2IAEA. Method for the Development of Emergency Response Preparedness for Nuclear or Radiological Accidents. IAEA-TECDOC-953,1997.
  • 3IAEA. Generic Assessment Procedures for Determining Protective Actions during a Reactor Accident. IAEA-TECDOC-955,1997.
  • 4IAEA. Intervention Criteria in a Nuclear or Radiation Emergency. Safety Series No.109. IAEA,Vienna. 1994.
  • 5IAEA. Method for the Development of Emergency Response Preparedness for Nuclear or Radiological Accidents. IAEA-TECDOC-953.Vienna. 1997.
  • 6IAEA. Generic Assessment Procedures for Determining Protective Actions During a Reactor Accident. IAEA-TECDOC-955.1997.
  • 7U.S. Commercial Nuclear Power Plants. WASH-1400(NUREG75/014). Washington. 1975.
  • 8Queniart D, Sugier A, Lochatd J. Consideration of Postaccident Consequences in the Determination of Safety Objectives for Future Nuclear Power Plants in France.Nuclear Safety, 1994. 35(2) : 147.
  • 9IAEA. Generic Procedures for Assessment and Response during a Radiological Emergency. IAEA-TECDOC-1162.Vienna. 2000.
  • 10U. S. NRC. RASCAL Version 2.1. Users Guide.NUREG/CR5247.Vol 1. Rev. 1994.

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