快堆钠仪表技术

一、概述自从1946年世界上第一座快中子反应堆——美国的 Clementine 投入运行以来,液态钠冷却的快中子反应堆已经历了实验性快堆和原型快堆核电站两个发展阶段,目前已进入工业规模的快堆核电站发展阶段.苏联的电功率为600MW 的 BN600快堆核电站已于1980年4月并入电网,法国电功率为     

俄罗斯核战略的关键：BN-800快中子增殖堆

【英国《国际核工程》2005年3月刊报道】俄罗斯BN-800快堆项目将满足21世纪核电面临的更加紧迫的新要求,包括防扩散要求。钠冷却快中子反应堆已经被选为实施《21世纪上半叶俄罗斯核电发展战略》的堆型。专家们关注的焦点目前主要集中在如何使这种堆型具有经济竞争力,并创建闭合燃料循环工业。目前正在乌拉尔斯维尔德洛夫斯克地区别洛雅尔斯克核电厂建造的新型BN-800反应堆将在完成上述两项任务中发挥重要作用。BN-800项目是俄罗斯开发的钠冷快堆的一种后续堆型,其开发基础是前后三代钠冷快堆的设计和运行经验。BN-800主要基于在以前的BN…     

CEFR和BN800系统运行工况的分析和比较

研究反应堆系统的运行工况,对于反应堆的安全运行是非常重要的,本文对我国实验快堆CEFR和俄罗斯BN800快堆的总体特征进行了比较,并对CEFR和BN800的系统运行分类情况进行了比较分析,在此基础上,对CEFR和BN800系统的主要运行工况进行了细致的比较和分析,详细地分析了两个反应堆系统在各种运行工况下运行的要求、工况参数和运行过程以及相应的各项安全要求,比较分析了它们之间的相同之处和区别所在。     

俄罗斯将恢复快堆建造

【日本《原子能产业新闻》2001年3月1日报道】 根据俄罗斯原子能学会2月13日在媒体上发表的消息,俄罗斯原子能部部长Y·阿达莫夫和斯维尔德洛夫斯克地方长官E·罗塞尔最近达成协议,将在年内恢复建造别洛雅尔斯克核电站4号机组,该机组是功率为800 MW的BN-800型快堆。 自1997年法国的超凤凰堆关闭以来,在斯维尔德洛夫斯克的别洛雅尔斯克还有世界上唯一的商业规模的快堆——别洛雅尔斯克3号机组(系输出功率为600 MW的BN-600)在运行。在该厂址中断建造的4号机组已经通过了专家审查,5.7亿卢布的建造费用也已落实。该工程预定于2009年完成。该…     

俄罗斯BN-1200大型快堆建设项目获批

【世界核新闻网站2012年6月27日报道】俄罗斯斯维尔德罗夫斯克(Sverdlovsk)地方政府已批准在别洛雅尔斯克核电站建设俄首座BN-1200大型快堆,用来代替该厂址上现有的一座较小型快堆即BN-600快堆。     

中国核电规划与先进堆

本文论述了在制定中国核能长期规划时,研究世界先进堆技术发展趋势的必要性.作者认为,下个世纪热堆电站将还会有一个相当长时期的发展阶段。而在下世纪初,第二代核电站可能形成一种新的潮流,这些新一代先进堆都具有固有安全和非能动安全特性的设计新概念.其中最有希望的是 AP-600和 MHTGR。中国专家们正在严密注视和紧紧跟踪这两个方向.     

核电发展的第二代——快中子增殖堆核电站

本文第一部份简要说明第一代核电站堆型发展的局限性和发展快中子增殖堆的必要性。第二部份通过国际快堆经验论证和说明了快堆是安全性好,可靠性强,且有好的经济前景的堆型。第三部份对我国快堆发展战略和技术路线提出建议。最后指出了在所提战略下我国核电发展的前景。     

俄罗斯将继续建造快堆电站

[《瑞士原子能协会通报》1994年第11期第9页和欧洲核学会《核新闻网》1994年5月25日报道] 据俄罗斯原子能部(Minatom)最近称,重新开始建造南乌拉尔斯核电站(SUNPP)的工程现在已不存在任何障碍。该核电站位于乌拉尔工业区的车里雅宾斯克的马亚克中心,计划建造3套大型BN—800型快中子增殖堆机组。     

中国示范快堆技术选择探讨

我国快堆下一步的发展,具备商用核电站功率规模的示范性大型快堆的研发是一个必然趋势。由于中国实验快堆的技术方案在很大程度上已经非常接近商用堆参数,这使得在示范快堆的技术选择上有较多的经验可以借鉴。总的来说,示范堆的技术选择是参照第四代核能系统的部分目标,结合中国的实际进行最终选择的结果。     

AP1000反应堆——核能复兴方案

AP1000是一种二环路、1150MWe的压水堆；它具有提高电站建造、运行和维修性能的非能动安全阳广泛的电站简化特点：APl000设计直接源自于AP600——一种二环路、600MWe的压水堆．AP600采用已验证的技术，在30多年压水堆运行经验的基础上建造。1998年9月，美国核管会批准了AP600的最终没计；1999年12月颁发了设计资格证书．AP600满足电力研究所(EPRI)的先进轻水堆用户要求，包括成本目标，随后的高水平评审也表明与欧洲用白要求文件达到广泛的一致。尽管AP600是准备应用的成本．效益最好的电站，但是它仍然比需要在目前美国和欧洲竞争的1000美元/kWe的基础价更昂贵。为了提供成本一竞争的核电站，西屋公司研究了将AP600的功率提高到至少1150MWe．而保持其原有的设计布局，使用已经验证的设备和取证基础。最近．西屋公司与英国能源公司已经合作完成了一项研究，评定将AP1000反直堆作为建造在英国的新核电站的一个方案。     

用于海上钻井平台的小型钠冷快堆核电源概念设计方案

根据海上石油钻井平台用户电力需求的特点,介绍了一种基于斯特林热气机发电技术的小型钠冷快堆核电源设计方案,研究了小型钠冷快堆核电源的总体技术方案、主回路冷却系统以及关键设备设计方案,并给出小型钠冷快堆核电源的初步布置方案。研究结果表明：小型钠冷快堆核电源概念设计方案符合海上石油钻井平台用户需求的长周期换料、空间限制等特点。     

我国的快堆技术发展和实验快堆

随着我国核电技术的发展,自主研制钠冷快中子增殖堆十分必要。本文介绍了我国在研究开发快堆技术方面的历史和实验快堆的设计原则、设计简介和安全特性。     

田湾核电站失去厂外电源事故处理

考虑到核电站在安全方面的重要性,在核电站的厂用负荷电源的设计中,通常设计为多电源的冗余配置,以保证在事故工况下维持核反应堆的安全和放射性的包容。因此,在田湾核电站的设计中,厂外电源就包括了从500kV侧引入的主电源和从220kV侧引入的备用电源。如果两路外电源同时失去的情况下,将只能依靠电站本身的安全系统柴油机来维持反应堆堆芯的安全,将对机组的安全系数产生较大的影响。针对2009年10月31日田湾核电站1号机组满功率情况下发生的同时失去所有厂外电源的事故隋况,阐述运行人员应如何应对和处理这种事故,以达到反应堆安全停堆的效果;并针对实际过程中发生的异常,探讨系统改进及操作方面的优化。     

Actinide breeding and reactivity variation in a thermal spectrum ADSR – Part 1: Development of a lumped thermal reactor model

The beneficial properties of fast reactor systems in being able to both burn and breed actinides have led to renewed interest in this technology as a means of providing a more sustainable form of nuclear power production. However, despite significant investment over many years in the development of the technology, fast reactors have never been deployed in significant numbers. In view of the difficulties encountered in fast reactor development, enhancements to the existing, well proven light water reactor (LWR) technology may provide a more accessible path to improved sustainability.     

快堆核燃料循环模式的经济性评价

以快堆核电厂的核燃料循环过程及核燃料循环模型为基础,利用注销法对2种核燃料循环方式进行经济性计算和分析;同时,也将快堆燃料循环经济性与压水堆(PWR)燃料"一次通过"的经济性进行对比。按目前价格水平计算,PWR"一次通过"的核燃料循环方式比快堆核燃料循环模式的经济性好,但随着天然铀价格的上涨以及燃料后处理技术水平的进步,快堆核燃料循环费用有望达到或低于PWR"一次通过"的核燃料循环费用。     

“中国示范快堆项目”介绍

结合目前＂快堆＂升温的情况,简要介绍了＂中国示范快堆项目＂的拟选厂址情况,包括位置、气象和地质等。以期引起大家对快堆的商用进展情况的关注。     

核电站反应堆冷却剂系统主管道安装焊接

以秦山核电二期工程为例,论述了核电站反应堆冷却剂系统主管道安装焊接技术及质量控制要点,并对反应堆冷却剂系统主管道的安装顺序、安装技术要求、焊接质量检验方法以及焊接变形的控制等方面给予了详细的阐述,对核电站反应堆冷却剂系统主管道安装焊接及质量控制具有借鉴作用。     

Nuclear fuel considerations for the 21 century

There are many external influences that may control the path that nuclear power deployment follows. In the next 50 years several events may unfold. Fear of the consequences of the greenhouse effect may produce a carbon tax that would make nuclear power economically superior very quickly. This, in turn, would increase the rate at which uranium reserves diminish due to the increased rate of nuclear power deployment. However, breakthroughs in the extraction of uranium from the sea or deployment of fast breeder reactors would greatly extend the uranium reserves and, as well, utilize the thorium cycle.On the other hand, carbon sequestering technology breakthroughs could keep fossil fuels dominant for the remainder of the century. Nuclear power may only then continue, as today, in a lesser role or even diminish. Fusion power or new developments in solar power could completely displace nuclear power as we know it today.Even more difficult to predict is when the demand for mobile fuel for transportation will develop such that hydrogen and hydrogen rich fuel cells will be in common use. When this happens, nuclear power may be the energy source of choice to produce this fuel from water or methane. In a similar vein, the demand for potable and irrigation water may be another driver for the advent of increased deployment of nuclear power.With all these possibilities of events that could happen it appears impossible to predict with any certainty which path nuclear power deployment may take. However, it is necessary to define a strategy that is flexible enough to insure that when a technology is needed, it is ready to be deployed.For the next few decades there will be an evolutionary improvement in the performance of uranium oxide and mixed uranium oxide-plutonium oxide (MOX) LWR fuels. These improvements will be market driven to keep the cost of fuel and the resulting cost of nuclear power electricity as competitive as possible. The development of fuels for accelerator transmutation and for reactor transmutation with inert matrix fuels is in its infancy. A great deal of research has been initiated in a number of countries, which has been summarized in recent conferences. In Europe the work on these fuels is directed at the same problem as their utilization of MOX; namely to reduce the inventory of separated plutonium, minor actinides, and Long Lived Fission Products (LLFP). In the United States there is no reprocessing and thus no inventory of separated civilian plutonium. However, in the United States there is a resistance to a permanent spent fuel repository and thus accelerator transmutation presents a possible alternative. If nuclear power does have a long-term future, then the introduction of the fast reactor is inevitable. Included in the mission of the fast reactors would be the elimination of the inventory of separated plutonium while generating useful energy. The work that is ongoing now on the development of fuel concepts for assemblies that contain actinides and LLFP would be useful for fast reactor transmutation.There is still a great deal of work required to bring the fast breeder reactor option to maturity. Fortunately there is perhaps a fifty-year period to accomplish this work before fast breeders are necessary. With regard to fast reactor fuel development, future work should be considered in three stages. First, all the information obtained over the past forty years of fast reactor fuel development should be completely documented in a manner that future generations can readily retrieve and utilize the information. Fast reactor development came to such an abrupt halt world-wide that a great deal of information is in danger of being lost because most of the researchers and facilities are rapidly disappearing. Secondly, for all of the existing fast reactor fuels, and this includes, oxides, carbides, nitrides, and metallic fuels, the evolutionary work was far from being completed. Although mixed oxide fuels were probably the furthest advanced, there were many concepts for improved claddings and advanced fabrication methods that were never fully explored. Finally, with such an extended period before fast reactors are needed there is ample time for truly innovative fuels to be developed that are capable of performing over a wide range of conditions and coolants.     

空间核反应堆电源热工水力特性研究综述

随着空间探索领域的快速发展,研究高功率、安全、可靠的空间核反应堆电源将变得愈发重要。本文针对国内外空间核反应堆电源的热工水力关键问题,即空间堆系统稳态和事故瞬态研究、堆芯单冷却剂通道及全堆芯的三维流动换热、静态与动态热电转换装置分析、热工水力特性试验研究等进行研究,分析了空间核反应堆电源热工水力研究的趋势。本文结果可为空间核反应堆电源设计分析及热工水力安全特性研究提供帮助和指导。