我国核电厂选址标准研究走向的思考被引量：1

Considerations on the Research Trend of the Siting Standards for Nuclear Power Plants in China

下载PDF

导出

摘要简要回顾了核动力厂选址适宜性准则的建立与发展,介绍了核动力厂厂址评价的新进展,探讨了核动力厂选址标准研究的走向。在制定我国核动力厂选址标准中,应优先建立厂址适宜性准则,包括厂址安全、环境保护和应急准备的各种要素,以指导厂址评价。 This article briefly reviewed the establishment and development of site suitability criteria for nuclear power plants, introduced the new progress for assessing site suitability and discussed the research trend of the siting standards for nuclear power plants. In the development of China＇ s nuclear power plant siting standards, priority should be given to the establishment of site suitability criteria, including the various elements such as site safety, environmental protection and emergency preparedness in order to guide the site evaluation.

作者陈晓秋侯杰李冰

机构地区环境保护部核与辐射安全中心

出处《辐射防护通讯》 2013年第2期1-7,共7页 Radiation Protection Bulletin

关键词厂址适宜性厂址安全环境保护应急准备 Site suitability Site safety Environmental protection Emergency preparedness

分类号 TM623.1 [电气工程—电力系统及自动化]

引文网络
相关文献

参考文献14

1USAEC. Summary Report of Reactor Safeguards Committee [S]. WASH-3, 1950.
2USNRC. Reactor Site Criteria[S]. 10 CFR Part 100, ht- tp ://www. nrc. gov/reading-rm/doc-collections/cfr/partl00/ full-text, html.
3The History of Nuclear Power Plant Safety[ R]. http ://use- rs. owt. com/smsrpm/nksafe/ Jackson I,.
4Jackson S. Siting New Nuclear Power Stations: Availability and Options for Government[ R]. http ://www. berr. gov. uk/files/file39030, pdf.
5Dinunno J J, Anderson F D, Baker R E, et al. Calcula- tion of Distance factors for Power and Test Reactor Sites JR]. Technical Information Document 14844, http:// pbadupws, nrc. gov/docs/ML0217/ML021750625, pdf.
6USNRC. General Site Suitability Criteria For Nuclear Pow- er Stations[ S]. Regulatory Guide 4.7 Rev.2, 1998.
7USNRC. National Report for the Convention on Nuclear Safety[S]. NUREG-1650, 2001.
8IAEA. Site Evaluation For Nuclear Installations[R]. NS- R-3, 2003.
9USNRC. General Site Suitability Criteria For Nuclear Pow- er Stations[S]. Draft Regulatory Guide DG-4021, 2011.
10USNRC. Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors [ S]. Regulatory Guide 1.3 Rev.2, 1974.