美国核管会关于小型模块堆厂址人口要求的考虑及启示

本文介绍了美国核管理委员会(NRC)关于反应堆选址过程中与人口因素相关的审管要求和评估准则,详细分析了NRC针对小型模块堆对涉及厂址人口要求法规的4种修订方案,提出我国在制定小型堆厂址人口要求过程中需要关注的问题:(1)考虑到总体社会风险并从厂址比选的角度出发,建立一个恰当的反应堆距人口集中居住区(或人口中心)边界的距离是必要的。此外,从纵深防御考虑,小型堆厂址仍然需要与人口集中居住区保持一个适当的距离;(2)基于小型堆选址事故后果及影响范围,建立与大型商用核动力厂相同社会风险水平的评价指标(如事故工况下厂址周围的集体有效剂量)是有益的;(3)公众可接受性和选址政策也是小型堆能否靠近人口集中居住区的重要因素。     

核动力厂选址假想事故源项的探讨

介绍了美国核审管部门对核动力厂选址假想事故源项确定的历史演变以及相关研究进展。推荐了一套核动力厂选址假想事故源项,以及确定非居住区边界的评价分析方法和假设条件。计算了M310和AP1000核动力厂厂址的非居住区的最大径向距离。计算结果表明:(1)对于M310和AP1000核动力厂,采用确定论方法估算大气扩散因子,安全壳泄漏率(体积分数)取0.3%/d,非居住区最大径向距离分别不超过1.4 km和1.9 km;(2)在厂址选址阶段,考虑核动力厂的技术路线尚未明确或采用新技术路线,采用"不考虑安全壳喷淋系统等能动安全设施对核素的去除作用"的选址假想事故源项来确定厂址非居住区的边界基本上是可行的。     

核动力厂厂址地质调查工作的要求

本文简要地介绍了核动力厂厂址地质调查工作的主要内容、基本要求、阶段划分和各阶段要求调查的内容。并且根据现行的核安全法规要求,阐明了各项调查内容的调查目的及所要求的调查范围、深度和应提出的成果。     

英国确定11个新核电厂候选厂址

英国政府已公布了一份包含11个新核电厂候选厂址的清单,这些候选厂址是通过战略选址评价（SSA）程序提名的。     

核电厂选址放射性后果分析的几个问题

厂址安全、环境保护和应急准备是评价核电厂厂址适宜性主要关注的3个方面.本文概述了核电厂选址法规的基本要求,以及目前核电厂选址放射性后果分析中存在的问题,对选址阶段放射性后果审查中应当注意的几个问题进行了讨论.     

东源核电厂址(候选)水文地质条件初探

从地下水形成的自然条件,地下水赋存条件及分布规律,地下水类型,地下水的补给、径流、排泄,地下水的渗透性评价等方面出发,论述了东源核电厂址水文地质条件的适宜性。     

核动力厂应急行动水平的发展与应用

核动力厂的应急行动水平是核动力厂应急状态的分级判据.本文介绍了应急行动水平的发展情况及我国各核动力厂所使用的应急行动水平的特点,并对其中的差异进行了比较分析,对目前我国核动力厂应急行动水平中辐射报警阈值设定、屏障丧失判断、外部程序引进和多机组厂址分级特点等问题进行了讨论.     

高放废物处置区域尺度岩体适宜性评价研究

岩体适宜性评价是高放废物处置库选址和设计的重要工作内容,以判断场址岩体是否满足处置库长期包容和隔离核素的功能要求。依据我国的高放废物处置概念和场址条件,提出了Q_HLW岩体适宜性评价方法,但目前Q_HLW在场址尺度展开了较为深入的研究,尚未在处置区域尺度、处置巷道及处置坑尺度建立完善系统岩体适宜性评价方法。结合芬兰地下实验室研究和处置库设计经验,建立处置区域尺度岩体适宜性评价准则Q^P_HLW,提出了裂隙带影响、地下水化学条件、岩体渗透特性、岩体强度应力比值以及岩体完整性等评价指标的取值方法,并确定岩体适宜性评价分级标准。随后,利用芬兰高放废物处置ONKALO地下实验室场址数据,测试和验证处置区域尺度岩体适宜性评价准则Q^P_HLW的合理性与可行性。最后以北山地下实验室新场场址为评价对象,开展处置区域尺度岩体适宜性评价,适宜性评价结果表明：新场场址在处置深度400～450 m及550～600 m内岩体完整性高,岩体适宜性程度高,适合布置处置巷道。     

苏联新建快堆核动力厂

【西德《原子与电流》1987年第2期第43页报道】苏联开始新建一座快堆核动力厂。据塔斯社报道,核动力厂的快堆功率为800MW,属于反应堆总功率可能扩大到1600MW 的新型核动力厂的结构系列。塔斯社未报道这座新的核动力厂的厂址。     

核电厂前期厂址选择的思路

从建设经济性、技术可行性、安全可靠性和环境相容性4个方面分析了核电厂前期选址的主要特征指标,并以红沿河核电厂为例,详细分析了核电厂安全、环境、社会经济和应急4个方面的特征指标以及量化评分情况。这种厂址特征指标选取和量化比较的分析思路,可以为核电厂前期的厂址比选提供有效的辅助。     

A systematic methodology approach for selecting preferable and alternative sites for the first NPP project in Yemen

The purpose of this paper is to present the results of the first siting study that was performed to investigate the availability of sites for a 1000 MWt nuclear power plant (NPP) project in Yemen. Only about thirty eight percent of the population in Yemen has access to electric power. This low access has negative impacts to quality of life as well as broad economic implications. Although the political and security situation in Yemen is still unstable, the government of Yemen looks forward to the future and has been developing plans to replace aging electric power infrastructure, to increase the grid capacity and to possibly add a nuclear power plant (NPP) of the 1000 MWt class to its current energy mix. This paper presents the results of a siting study for NPP in Yemen suggesting a PWR type (Pressurized Water Reactor). From eight coastal provinces twelve potential sites were proposed and then evaluated against nine avoidance criteria to screen out some candidate sites, then these sites evaluated again under other nine suitability criteria to choose the preferable and alternative sites. To perform this study in systematic approach using the Analytic Hierarchy Process (AHP) was applied to support the decision making analysis. Results showed that the southern coast of Yemen has the capability to accommodate nuclear power plants due to its large area and low population density. The siting study recommends three high preference sites and another three acceptable alternative sites.     

Soil site response

The response of stiff quaternary soil sites to strong earthquake shaking is an important factor in the development of seismic siting criteria for nuclear power plants. Analytical methods for estimating this site response are in common use, but there is need for empirical verification of these modeling techniques. There are two dense 3-D strong motion arrays installed and operating in California to directly measure the response of stiff quaternary soil to earthquake shaking. These are the Hollister Earthquake Observatory and the Borrego Valley Downhole Arrays. Site response measurements from these arrays, along with detailed geotechnical and geophysical site investigations, will provide important calibration and confirmation of site response modeling techniques used for seismic siting criteria development. This paper presents an overview of the two arrays and initial results of the measurements.     

Seismic design of nuclear power plants — an assessment

This paper presents a review and evaluation of the design standards and the analytical and experimental methods used in the seismic design of nuclear power plants with emphasis on United States practice. Three major areas were investigated: (a) soils, siting, and seismic ground motion specification; (b) soil-structure interaction; and (c) the response of major nuclear power plant structures and components. The purpose of this review and evaluation program was to prepare an independent assessment of the state-of-the-art of the seismic design of nuclear power plants and to identify seismic analysis and design research areas meriting support by the various organizations comprising the ‘nuclear power industry’. Criteria used for evaluating the relative importance of alternative research areas included the potential research impact on nuclear power plant siting, design, construction, cost, safety, licensing, and regulation.Three methods were used in the study herein. The first involved the review of current literature, focusing primarily on publications dated later than 1970. This review included the results of numerous studies, of which those of Japanese origin and those presented in recent international conferences were predominant. The second method entailed a review of international experience in the dynamic testing of nuclear power plant structures and components, and related experience with scaled and model tests. Included in this experience, in addition to the questions of analysis, design, and measurement of dynamic parameters, are related efforts involving a review of responses obtained during measured earthquake response and investigations into appropriate methods for backfitting or upgrading older nuclear power plants to meet new seismic criteria.The third approach was to obtain the opinions and recommendations of technically knowledgeable individuals in the US ‘nuclear industry’; the survey results are shown in the Appendix.     

Priorities for using low-capacity nuclear power plants in Eastern Russia

Studies validating rational variants of the development of energy supplies for distributed consumers in the eastern regions of Russia on the basis of the availability of energy resources, transport access, and economic efficiency are indicated in this article. The efficiency and site conditions for the best expansion of a centralized electricity supply, siting of mini thermal and power plants using local fuel, renewable energy sources, low-capacity nuclear power plants, and gas in gas-diesel electricity plants are presented. Proposals are made for developing rational schemes for supplying energy to consumers supplied from the Chaun-Bilibino power system in the Chukotka Autonomous District.     

新时期核电站厂址选择与项目前期管理研究

文章介绍了日本福岛核事故发生以后,我国核电站厂址选择工作面临的困难和挑战,分析了当前核电站厂址选择的要点,重点阐述了核安全相关厂址特征的选择与评价方法,并从项目管理的角度,论述了核电项目前期主要的流程和关键点.     

福岛核事故引发的若干思考

福岛核事故是一场损失惨重的核灾难,它提出了一些值得深入分析和思考的问题。文章对今后核电发展中遇到的选址（包括在选址后的几年内,定期观测和仔细研究核电厂周围区域的地震和地质条件的变化发展）、机组延寿、反应堆压力容器可能开裂和一址多堆等问题进行了简短的讨论。     

缺乏受纳水体区域核电厂液态流出物液转气排放的概念和应用原则

随着国家标准GB 6249—2011和GB 14587—2011的颁布实施,对具有受纳水体的内陆核电厂相关管理要求基本完善。近年来,一些核电集团公司陆续在缺乏受纳水体区域开展核电厂选址工作。本文针对我国缺乏受纳水体区域核电厂选址和建设的瓶颈问题,提出了液态流出物液转气排放概念,设想了几种液转气排放工艺,研究提出了液转气排放应用原则。     

Some current issues in operational transients

This paper presents a summary and comparison of current U.S. regulatory standards, including those developed by industry as well as government, which regulate the construction and operation of nuclear power plants, with those standards in other countries that have developed their own national standards. The countries besides the United States that have been reviewed and surveyed in this paper are Canada, the Federal Republic of Germany (FRG), France, Japan, Sweden, and the United Kingdom (UK). The standards considered are those associated with the areas of siting, mechanical and structural engineering, and materials.     

Summary and comparison of current U.S. regulatory standards and foreign standards

This paper presents a summary and comparison of current U.S. regulatory standards, including those developed by industry as well as government, which regulate the construction and operation of nuclear power plants, with those standards in other countries that have developed their own national standards. The countries besides the United States that have been reviewed and surveyed in this paper are Canada, the Federal Republic of Germany (FRG), France, Japan, Sweden, and the United Kingdom (UK). The standards considered are those associated with the areas of siting, mechanical and structural engineering, and materials.