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英国对国防核设施退役的监管 总被引:1,自引:0,他引:1
英国对其国防核设施采取的是外部监管与内部监管并行的方式,退役也是如此。本文简要介绍了英国国防核设施退役的监管格局与模式,相关的背景也有所交代。内、外部监管的联合已经逐步成型,内部监管至少在技术层面上正在向外部监管看齐,融合的趋势已经显现——虽然国防核设施以满足国家安全的需要为首要目的,但其退役及其监管与民用核设施基本上没有本质的差别。 相似文献
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2017年10—12月, 中欧核安全合作二期项目TASK-5“核设施退役监管方法及要求”在西班牙和法国的在职培训交流工作(0JT)顺利结束。由环境保护部(国家核安全局)、环境保护部核与辐射安全中心、RISKAUDIT, IRSN、TECNATOM等相关单位筹办, 通过授课、讨论会、实地访问等形式进行。 相似文献
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The Lungmen Nuclear Power Plant (LMNPP) is currently under construction in Taiwan, which consists of two Advanced Boiling Water Reactor (ABWR) units. The instrumentation and control (I&C) systems of the Lungmen NPS are based on the state-of-the-art modernized fully integrated digital design. The design and architecture of digital systems are inherently different from those of analog systems. We face challenges in areas where there is limited technical guidance and regulatory precedent. This paper presents regulatory overviews, regulatory requirements, current major regulatory issues, as well as the areas of regulatory concerns and the lessons learned on the digital I&C systems in the Lungmen Project. 相似文献
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笔者根据自己多年从事核安全监督管理的实践和学习核安全法规的体会,特别是根据笔者本人在地区核安全监督站的工作经历,阐述了关于我国核安全监督管理体系的某些个人观点. 相似文献
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AbstractThe regulatory driven design of radioactive material transportation packages leads package vendors to perform analyses that demonstrate the ability of packages to meet the regulatory requirements. For risk assessment and communication, the analysis of package response to thermal environments that are more severe than those described in the regulations is required. In general, experimental and analytical assessments of casks exposed to thermal insults other than the regulatory environment are performed in the USA by the Department of Energy national laboratories. This paper provides a brief summary of some recent thermal analyses of spent fuel transportation packages exposed to thermal environments different from regulatory standards. The analyses were performed by Sandia National Laboratories under several different projects for multiple customers. These analyses examined the response of spent fuel packages exposed to severe thermal environments different from the regulatory hypothetical accident condition. One assessment determined the response of four generic casks to very long duration engulfing fires. The results from these analyses included fire durations necessary to reach critical temperatures of the fuel and seals. In another assessment, two certified spent fuel casks were analysed for exposure to 1 h pool fires. The height of the cask above the pool was varied to study the effect of the vapour dome on the heating of the casks. Another assessment investigated the effect of offset long duration fires on rail cask performance, which showed that casks can withstand offset fires of much longer duration than the regulatory fire. Other assessments examined the response of packages to thermal environments resulting from propane fires and realistic liquid hydrocarbon fires that included various positions of the transportation rail car in the simulation. 相似文献
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Andrei Blahoianu Thomas Viglasky Colin D. Moses Ken Kirkhope 《Nuclear Engineering and Design》2011,241(3):548-554
Effective ageing management is a key element of the strategy for maintaining long-term safety and reliability of nuclear power plants (NPP). This paper presents the Canadian regulatory perspective on managing the ageing of CANDU NPP. This paper looks introspectively at the current level of ageing management effort at Canadian reactor sites, and discusses the need to increase efforts in order to account for the increasing effects of degradation mechanisms. It examines accepted international practice for ageing management, making reference to International Atomic Energy Agency (IAEA) suggested practice, and goes on to describe the overall Canadian regulatory approach to ageing management, including the development of regulatory requirements for ageing management programs. In conclusion, the paper indicates a path forward involving a proactive ageing management approach. 相似文献
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This paper describes the overall licensing process in Spain, focusing on the initial commissioning requirements. The significance of this part of the regulatory work is evident both from the licensing and the licensee's points of view.Licensing in Spain is ruled by different laws which determine the general requirements and fix the licensing frame. Being a nuclear technology importer country, the base of the regulatory work lies on the rules and regulations of the country of origin of the plant, with the addition of case specific requirements. The application of this methodology to plants designed in different countries produces licensing processes which are similar in the overall, but very different in its development. It also means a special technical effort on the part of the regulatory body to cope with the problems arising from the use of different technologies and safety standards.The start-up programs from fuel loading to full power of a Westinghouse plant (Vandellós 2) and a Siemens-KWU plant (Trillo 1) are compared from the technical point of view, enhancing the differences that can be relevant for the regulatory work. The difficulties arising from the application of both the German and US concepts are discussed. 相似文献
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基于对计划照射中个人剂量约束概念的理解,讨论了个人剂量约束在公众照射和职业照射中的应用。在计划照射情况下,公众照射的剂量约束值通常由国家监管机构建立或批准;对于职业照射,鼓励在核能行业组织和核能集团内建立职业照射个人剂量约束值,比审管部门规定具体的约束值可能更合适。 相似文献