我国核电的可持续发展初探

对世界核能概况和我国的核能现状做了较深入的分析,并就我国核电可持续发展的问题提出了若干建议;同时以广三核作为核电国产化的驱动项目,预测了我国核电发展的前景。     

核能在我国能源战略中的地位

本文回顾和分析了中国与世界核能发展的历史及现状 ,系统地阐述了核电在我国能源战略中的地位和作用     

公共安全与低碳经济双重约束下的核能发展模式及路径研究

核能以其清洁、安全、持续、高效为人类提供了17%的能源供给。我国正处于工业化进程的关键时期,发展核能既是经济高速发展和能源安全的需要,也是保护生态环境、履行国际义务的需要。为了最大限度地保证核能安全、高效运行,各国都从技术研发投入,核能监管法制化、运作市场化,社会责任评估和风险预警机制以及公众宣传等方面进行模式创新。我国核能发展正面临着公共安全和低碳经济的双重约束,必须坚持"在确保安全的基础上高效发展核电"的方针,变"适当发展"为"积极发展"。需要改革核能管理体制;加大人才培养和联合研发力度;采取积极的产业政策,按市场规律盘活现有资金;建立社会影响评价和风险准备金机制;采取更为严格的标准重新评估所有核电站厂址安全,借鉴国际先进管理经验制定核电站的安全管理政策;评价和进一步加强在役及在建核电站的安全预警系统;做好公众核知识科普宣传工作,提高公众参与核能发展决策的意识以及对核事故的应急响应能力。     

世界铀的需求大幅增长

2009年末欧盟（EU）27国中15个国家运转的核能发电厂机组共144台,约占世界的1／3,超过北美的122台,居世界首位。曾经是“脱核电”先进地区的欧洲．重新涌现“核电复兴”浪潮。EU核燃料市场占世界的1／3。欧洲核能共同体（UERATOM）供应局（ESA）,     

加快开发我国核能产业实现能源结构多样化

伊拉克战争后的石油形势凸显我国能源安全方面潜伏的危机,主要表现为我国未来能源需求与能源资源储量不足之间的矛盾。同时,我国能源结构中以化石燃料为主所造成的环境问题也应引起高度重视。分析了核能的优势及其在我国能源发展中的地位,简要展望了我国核能发展的前景,探讨了影响我国核能发展的某些因素,在此基础上,从统一规划、实现我国核能产业的国产化和标准化角度对加快我国核能发展提出了一些建议。     

中国核能进入规模化发展新时期

<正>第二十五届国际核工程大会7月3日在上海开幕,主题为"核能——清洁、绿色、可靠的能源"。中国核能已进入规模化发展新时期,到2020年,我国核电运行和在建装机将达到8 800万k W,包括第三代核电技术在内的科技创新成果已领先国际先进水平,正逐步成为世界核电的产业中心。国际核工程大会素有核工程领域"奥林匹克"之称,是国际核工程领域最具影响力的大会。本次大会是第四次由中国举办,充分体现了国际同行     

美国核能辩论现状与政策趋向分析

美国国内在是否利用核能发电这个问题上一直存在争议,拥核派和反核派的分歧主要是在核电成本是否高、核能是否安全以及核能是否属于清洁能源等方面。受日本核危机影响,美国核能辩论的重点转向核能安全,主要围绕核电站抵御自然灾害的能力、核废料储存、是否应该新建核电站以及延长现有核电站运营期限等问题展开。由于历次重大核事故后,新建核电站成本势必上升,加之美国各州新建核电站积极性不高,国际大环境也不利于拥核派,同时核能面临化石能源和可再生能源的激烈竞争,因此短期内美国核能开发步伐势必会放慢。但是从长期看,核能仍将是美国能源战略的重点之一,究其原因,发展核能是美国能源安全与经济发展的需要,也是应对气候变化的需要,另外,拥核派的积极游说和公关行动、反核派内部立场出现分化以及日本核危机的长期影响有限等也都是其原因之一。我国是世界上在建核反应堆数量最多的国家,但是围绕核能的公开辩论却很少,这不利于我国核能的开发。核能的辩论过程,也是核能知识普及的过程,只有对核能有深入全面的认识,才能减少对核能非理性的恐惧。我国绝不能因为一次核事故而改变战略方向,而应在吸取教训的基础上,在保证绝对安全的前提下,继续发展核能。     

我国大陆核电装机容量超5500万kW

正截至2018年7月份,我国大陆核电总装机容量5500多万kW,名列世界第4。其中在运核电机组34台,在建核电机组20台。在建核电机组规模居世界首位,是世界上核电发展最快的国家。中国核学会理事长李冠兴25日在杭州召开的第九届国际青年核能大会上表示,中国积极发展绿色核能,已经形成了被国际社会广泛认可的"中国经验"。     

国内外乏燃料后端处理

对乏燃料进行安全环保的后端处理是核能健康发展的可靠保障,我国和国际核电先进国家都对此十分重视。分别从总体需求、储存、运输现状等方面介绍了国内外乏燃料后端处理现状和发展趋势。     

我国新能源科技成果现状研究与未来发展建议

新能源产业是我国"十二五"期间重点发展的战略性新兴产业之一,汇总分析21世纪以来我国新能源技术的科技成果,揭示其研发现状及发展趋势十分必要。利用文献计量、数据对比、数值模拟计算等分析方法,对我国以及中国科学院2000年以来在先进核能、太阳能、风能和生物质能领域的科研成果产出数量、年度分布、技术分类等进行计量分析。2006~2008年是新能源技术科技成果数量快速增长的时期,生物质能的科技成果产出最多,太阳能和风能次之,核能的科技成果产出最少,比较符合我国实际国情下发展高效安全能源的思想和策略。北京、上海、辽宁和广东是主要成果产出地区。中科院和南开大学、清华大学等是主要成果产出机构,中科院在生物质能、风能领域的科技成果优势较为突出,但仍需在太阳能、核能领域加强技术研究。为促进新能源产业的发展,我国应进一步完善新能源产业发展规划;提高新能源产业"软"、"硬"两方面的技术,缩小与国外先进水平的差距;建立新能源产业资金和运营保障体系;完善新能源价格政策;加强基础研究,促进产学研结合,完善新能源科技创新体系。     

AP1000安全壳的优越性分析

福岛事故后,公众对于核电厂的安全性更加关注。而反应堆安全壳作为核电站最后一道安全屏障,其主要功能是能够在反应堆正常运行期间及事故工况下包容壳内的放射性物质,以避免对周围环境及社会公众造成危害。主要介绍第三代核电站AP1000的安全壳系统,并通过与现有二代堆安全壳对比的方式来论述AP1000安全壳系统的优越性。     

History of the PWR and its worldwide development

Pressurized water reactors and the US company Westinghouse are sometimes seen as synonymous with automobiles and Ford, or computers and IBM. It is certainly true that PWRs of Westinghouse design have a dominant position in the world market for nuclear power plants, but the situation is not directly comparable for a number of reasons. First, a nuclear power plant is not a clearly defined product and, even with a high degree of standardization of the reactor, it calls for a considerable amount of individualized engineering design to incorporate it into the overall complex of a power station and to meet the licensing requirements of different countries. Moreover, while Westinghouse has played the leading role, many others organizations in different countries have contributed significantly to the development of the PWR from its earliest days and are playing an increasing role in its further development and exploitation. In addition, the hardware content of a nuclear power plant, including the reactor, incorporates components from many different manufacturers. What can be said, however, is that the basic configuration of the Westinghouse design of PWR is now so widely adopted that there is a unique worldwide fund of design, manufacture, construction and operating experience.     

The Penn State intelligent distributed control research laboratory

The authors describe the intelligent distributed controls research laboratory in the College of Engineering at Pennsylvania State University (PSU). The centerpiece of equipment is a modern distributed microprocessor-based control system which was interfaced to real-time simulations of power plant processes. Implementation issues of hierarchical and distributed control for large-scale power plant systems were more fully explored at the university level. The microprocessor-based control system has also been interfaced to the PSU TRIGA nuclear research reactor and enables research in optimal, robust, intelligent, and other advanced control techniques for nuclear power plants     

Using next generation nuclear power reactors for development of a techno‐economic model for hydrogen production

Nuclear and hydrogen are considered to be the most promising alternatives energy sources in terms of meeting future demand and providing a CO?‐free environment, and interest in the development of more cost‐effective hydrogen production plants is increasing—and nuclear‐powered hydrogen generation plants may be a viable alternative. This paper is a report on investigating the application of new generation nuclear power plants to hydrogen production and development of an associated techno‐economic model. In this paper, theoretical and computational assessments of generations II, III+, and IV nuclear power plants for hydrogen generation scenarios have been reported. Technical analyses were conducted on each reactor type—in terms of the design standard, fuel specification, overnight capital cost, and hydrogen generation. In addition, a theoretical model was developed for calculating various hydrogen generation parameters, and it was then extended to include an economic assessment of nuclear power plant‐based hydrogen generation. The Hydrogen Economic Evaluation Program originally developed by the International Atomic Energy Agency was used for calculating various parameters, including hydrogen production and storage costs, as well as equity, operation and maintenance (O&M), and capital costs. The results from each nuclear reactor type were compared against reactor parameters, and the ideal candidate reactor was identified. The simulation results also verified theoretically proven results. The main objective of the research was to conduct a prequalification assessment for a cogeneration plant, by developing a model that could be used for technical and economic analysis of nuclear hydrogen plant options. It was assessed that high‐temperature gas‐cooled reactors (HTGR‐PM and PBR200) represented the most economical and viable plant options for hydrogen production. This research has helped identify the way forward for the development of a commercially viable, nuclear power‐driven, hydrogen generation plant.     

ABWR核电机组热经济性分析的扩展型EEDM方程

以先进型沸水堆(ABWR)核电机组热力系统为研究对象,在常规火电机组热力系统热经济性分析的能效分布矩阵方程(EEDM)的基础上,结合ABWR核电机组热力系统的特点,经过理论分析和数学推导,构建了适合ABWR核电机组热经济性分析的扩展型EEDM方程,并通过实例对方程的正确性进行了验证。     

我国亟需尽快启动快堆核能系统的技术开发

本文概述核能对保障我国能源安全从而促进国民经济可持续发展的重要作用,指出我国的压水堆核电技术从第二代向第三代发展,总体上可以说是“今天”核电产业的技术升级工程。快堆及其燃料闭合循环可以充分利用铀资源和实现核废物的最少化,从而保证核裂变能的可持续发展。作者强调,我国核能科技的发展战略不仅要重视“今天”的核电产业的技术升级,更应着眼于“明天”的核能产业的技术开发。尽快启动我国快堆核能系统的技术开发具有极其重要的战略意义。     

Supply of appropriate nuclear technology for the developing world: Small power reactors for electricity generation

A growing world population, expected to reach eleven thousand million people by the year 2050, implies a growing need for the expansion of energy conversion technology. Over 80% of the world's population growth is projected to be centred in the lesser developed countries (LDCs), that part of the world expected to experience the largest growth rates in energy consumption. Constraints on fossil fuels, such as oil, natural gas and coal, imply that other energy sources will be needed in large supply to fulfill LDC energy demands. This paper reviews the supply of small nuclear power plants (200 to 500 MWe electrical generating capacity) available on today's market, including the pre-fabricated designs of the United Kingdom's Rolls Royce Ltd and the French Alsthom-Atlantique Company. Also, the Russian VVER-440 conventionally built light-water reactor design is reviewed, including information on the Soviet Union's plans for expansion of its reactor-building capacity. A section of the paper also explores the characteristics of LDC electricity grids, reviewing methods available for incorporating larger plants into smaller grids as the Israelis are planning. Future trends in reactor supply and effects on proliferation rates are also discussed, reviewing the potential of the Indian 220 MWe pressurised heavy-water reactor, South Korean and Japanese potential for reactor exports in the Far East, and the Argentine-Brazilian nuclear programme in Latin America. This study suggests that small reactor designs for electrical power production and other applications, such as seawater desalination, can be made economical relative to diesel technology if traditional scaling laws can be altered by adopting and standardising a pre-fabricated nuclear power plant design. Also, economy can be gained if sufficient attention is concentrated on the design, construction and operating experience of suitably sized conventionally built reactor systems.     

Small nuclear power plants: Financing ease may balance scaling factor

Economies of scale are highly significant for conventional light water nuclear power plants, but large units have become very difficult to finance for US utilities. If a small reactor with not quite such an unfavourable scaling factor could be designed, would it find a market? A modelling exercise, in which a hypothetical utility meets its capacity needs by building either 400 MW or 1200 MW nuclear plants, suggests that it might, under the right conditions. The model showed that the economies of scale of large plants tend to be overcome by financing difficulties which are avoided if small units are built. A small reactor would not be in the market alone, however. Competing with it would be other fuels and technologies, as well as the options of joint ownership of large plants, and purchased power.     

我国核电及核能产业发展前景

从减排、能源结构调整、环境保护角度分析核电在我国能源结构和我国科技体系中的定位及核电发展的必要性,根据我国运行核电厂的实际情况和自主设计的先进核电厂特性说明核电的安全性,同时根据运行核电厂放射性排放数据论述核电厂对环境和公众不造成任何有害的影响,并对核燃料循环、核废物对策和处理措施进行了论述。预测核电中长期发展情景,通过评估核电及配套核燃料产业能力,以及装备及相关行业发展情况,表明我国工业基础能够支撑核电的规模化发展;并反过来,核电将促进相关行业大发展,提高其技术水平,高科技含量,发展成高端产业,有利于我国经济转型。     

Predictability of safety analysis codes for departure from nucleate boiling in bundle for safety evaluation of massive hydrogen production systems

The advanced water reactor was indicated as a candidate for massive hydrogen production system using the water electrolysis method. In order to utilize the advanced water reactor system for hydrogen production, it is crucial to demonstrate the safety of the nuclear system during normal operations and accidents. Departure from nucleate boiling (DNB) is a critical phenomenon in the reactor core which should be addressed to demonstrate the integrity of the nuclear core during normal operations and accidents. Therefore, DNB has a particular importance to the reactor safety and precise prediction has been required for thermal-hydraulic analysis codes including subchannel and safety analysis codes. In this study it has been assessed the DNB prediction capability of thermal-hydraulic safety analysis codes used for the safety evaluation of nuclear reactor system against experimental data. For the assessment, thermal-hydraulic safety analysis codes, MARS-KS and TRACE, have been utilized. The DNB experiments conducted at the NUPEC experimental facility have been employed as a reference experiment for assessment. All experiments with bundle geometries under various steady-state conditions have been analyzed. The results show that both safety analysis codes generally predict the DNB power lower than the experimental database by 20% and the under-prediction occurs systematically with a linear characteristic. It is found that no significant difference in predictability of the DNB occurrence is observed between MARS-KS and TRACE. Therefore, it is concluded that both codes predict DNB conservatively, and MARS-KS and TRACE have almost identical predictability for the DNB occurrence.