共查询到19条相似文献,搜索用时 203 毫秒
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核事故和辐射事故的应急干预水平和应急防护措施决策问题 总被引:3,自引:1,他引:2
本文介绍了ICRP和IAEA最新推荐的应急干预原则和干预水平,讨论了各个国家和场址根据自己的具体情况确定自己的干预水平的必要性,并以日本为例用人力资本法估算了干预水平,最后讨论了应急防护措施决策的问题,给出了一般的决策方框图。 相似文献
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一个核事故应急防护决策计算机优化筛选系统 总被引:1,自引:0,他引:1
在核事故应急吓,在什么时刻,采取什么规模和什么防护措施来保护公众是应急决策的任务。由于时间紧,心理压力大,影响因素繁多,只靠有脑和临时研究是很难得出优化方案的。计算机支持的,并建立在有大量数据的数据库和基本防护方案预先基础上的决策系统可以发挥很大作用。 相似文献
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在压水堆核电站应急计划和应急响应中,堆底熔穿事故占有重要位置。本文用法国核电厂事故源项S3(对应于堆底熔穿事故)计算了在典型气象条件下的场外放射学的后果,根据一般防护决策原则和我国颁布的干预水平,提出了保护公众的应急防护措施的建议。 相似文献
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决策支持系统的发展与核事故应急决策 总被引:3,自引:0,他引:3
决策支持系统是指根据事先建立的判定原则或模拟模型,在各种实际情形下为决策提供支持或最佳答案的计算机实时系统。核事故应急决策支持系统是将决策支持系统引入核事故应急防护措施决策工作中的产物。本文通过介绍决策支持系统的概念及其发展概况,以及国内外核事故应急决策支持系统,特别是RODOS的发展现状,讨论核事故应急决策支持系统今后发展可能存在的问题以及发展方向。 相似文献
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乏燃料后处理厂可能发生临界、放射性物质泄漏、火灾和爆炸等事故,营运单位需要建立相应的应急评价能力,配置针对上述事故的核应急评价系统。本文介绍了针对乏燃料后处理厂5种典型事故的三维可视化实时核应急评价与决策支持系统设计,该系统可基于工艺系统监测数据实现应急工况实时诊断,计算向厂房和环境释放的源项,基于应急预案开展应急响应流程管理,针对工作人员和公众防护策略开展防护行动分析等功能,并基于三维可视化技术实现应急评价结果和响应流程的动态展示。本系统可用于我国乏燃料后处理厂应急评价与决策支持,提升其应急准备与响应能力。 相似文献
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核事故应急中的决策方法 总被引:1,自引:0,他引:1
介绍核事故应急决策评价系统的构成。针对核事故早期决策问题,建立评价时所考虑的属性树,描述评价过程中采用的多属性决策方法,最后给出了计算的实例。 相似文献
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事故评价是核电厂应急状态下进行防护行动决策的重要技术基础.事故评价包括事故状态评价和事故后果评价两个方面.本文主要介绍事故状态评价技术在核事故应急决策中的应用情况. 相似文献
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The principles for implementing measures for protecting nuclear and radiation hazardous objects from external perturbations are formulated. A method is proposed for assessing the effectiveness of decisions made to increase the protection of objects taking account of the prediction of possible actions and losses from protective measures taken which are inadequate to the situation.The method takes account of the stability and protection parameters of objects and the characteristics of the means of protection (including the cost). It is suggested that the effectiveness of different variants of protective measures be assessed according to the economic benefit from implementation of these measures. 相似文献
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《Packaging, Transport, Storage and Security of Radioactive Material》2013,24(2):165-167
AbstractIn Egypt the national regulations for safe transport of radioactive materials (RAM) are based on the International Atomic Energy Agency (IAEA) regulations. In addition, regulations for the safe transport of these materials through the Suez Canal (SC) were laid down by the Egyptian Atomic Energy Authority (EAEA) and the Suez Canal Authority (SCA). They are continuously updated to meet the increased knowledge and the experience gained. The technical and protective measures taken during transport of RAM through SC are mentioned. Assessment of the impact of transporting radioactive materials through the Suez Canal using the INTERTRAN computer code was carried out in cooperation with IAEA. The transported activities and empty containers, the number of vessels carrying RAM through the Canal from 1963 to 1996 and their nationalities are also discussed. The protective measures are mentioned. 相似文献
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Itsumasa Urabe Takatoshi Hattori Takeshi Iimoto Sumi Yokoyama 《Journal of Nuclear Science and Technology》2013,50(2):136-149
Lessons learned from the TEPCO Fukushima No.1 NPS accident are discussed from the viewpoint of radiation protection in the situation of nuclear emergency. It became clear from the discussion that the protective measures should be practiced by taking into account the time profiles of the radiological disaster after the nuclear accident and that the land and coastal sea areas monitoring had to be practiced immediately after the nuclear accident and the communication methods to tell the public about the radiation information and the meaning of protective measures should be developed for mitigation of the sociological aspects of disaster impacts. And it was pointed out from the view point of practicing countermeasures that application of the reference levels, above which it was judged to be inappropriate to plan to allow exposure to occur, played an important role for practicing protective measures in an optimized way and that the quantities and units used for quantifying radiation exposure of individuals in terms of radiation doses have caused considerable communication problems. Finally, the occupational exposures and the public exposures that have been reported so far are shown, and it is concluded that there is no conclusive evidence on low dose exposures that would justify a modification of the radiation risk recommended by the International Commission on Radiological Protection. 相似文献
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分析了三门核电放射性气溶胶的潜在来源,介绍了放射性气溶胶的监测方案及方法,在对工作场所气溶胶污染水平进行监测和对人员可能接受的放射性物质的摄入量进行评估之后,提出了放射性气溶胶内照射的防护措施和建议。 相似文献
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反应堆如发生燃料破损,~(131)I等裂变气体会通过破损包壳释放到厂房中增加人员内照射风险。以CPR1000机组为例分析表明:即使1根燃料棒破损也会对工作人员带来内照射风险,破损达运行限值0.25%时,即使投运净化系统,也需对人员采取防护措施。本文结合实际核电厂运行经验探讨了放射性碘危害的控制和防护措施。 相似文献
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介绍了宇宙空间及空间站内的辐射环境,针对各类太空辐射,选用合适的屏蔽材料、选择发射时机和运行轨道躲避强太空辐射,合理采用各种辐射防护方法和生物化学防护剂进行防护。 相似文献