我国核燃料循环前端产业的现状和展望

在分析我国核燃料循环产业面临发展机遇的基础上,阐述了天然铀的保障供给、铀转化和铀浓缩、燃料制造领域等核燃料循环产业的现状以及面临的挑战,并对我国核燃料循环前端产业的发展方向进行了分析预测,针对如何应对挑战提出了相应的对策。     

我国核燃料循环前端产业的现状和展望

在分析我国核燃料循环产业面临发展机遇的基础上,阐述了天然铀的保障供给、铀转化和铀浓缩、燃料制造领域等核燃料循环产业的现状以及面临的挑战,并对我国核燃料循环前端产业的发展方向进行了分析预测,针对如何应对挑战提出了相应的对策。     

我国先进核燃料循环技术发展战略的一些思考

从核裂变能可持续发展的角度,分析了各种核燃料循环方式的特点,指出了核燃料“一次通过”方式不符合核能可持续发展战略。为了充分利用铀资源并实现核废物的最少化,快堆燃料闭式循环是核裂变能可持续发展的根本出路。本文在介绍了国内外核燃料循环关键技术研究现状和发展趋势的基础上,探讨了我国核燃料循环科技的发展战略,并指出了为实现上述发展战略目标应采取的若干措施。     

堆后核燃料循环的发展

堆后核燃料循环是充分利用核资源和保障核安全的重要环节.本文分析了堆后核燃料循环,包括辐照核燃料的运输、中间贮存、后处理,混合氧化物燃料制备及放射性废物最终处置的发展现状。根据核能发展规划,至2000年从我国核电站卸出的辐照核燃料估计达1900吨左右。在实现核能计划的同时,应相应地发展堆后核燃料循环。     

核燃料循环设施事故分析方法探讨

为推动我国核燃料循环设施的事故分析方法不断发展完善,对国内外核燃料循环设施事故分析方法的应用现状进行了研究和比较,对不同事故分析方法进行了对比和分析,并结合我国工程实践对事故分析方法的发展提出了建议。研究表明,国外核燃料循环设施事故分析已逐渐使用概率风险评价方法,由此,我国核燃料循环设施领域逐渐引入概率风险评价方法可能成为事故分析的发展方向。ISA(综合安全分析)方法既参照确定论方法进行了单个(类)事件序列的情景假设和后果分析,又参照概率论方法进行了事件序列的概率估算,具有较好的适用性和可操作性,因此,我国核燃料循环设施领域可优先采用融合了确定论和概率论两种方法特点的ISA方法。     

核燃料循环成本与核电的竞争力

国际市场核燃料价格变幻莫测,对我国核电的成本和发展产生影响,本文提出了控制整个核燃料循环成本的设想,以提升中国核电的竞争力,促进核燃料产业和核电产业的共同发展。     

我国压水堆装载MOX燃料对核燃料循环情景影响初步分析

为了满足持续增长的国家能源需求,核电将有更大规模的发展。本文对我国未来的核电发展和核燃料循环进行了情景研究,预测了2050年前核电对天然铀资源和燃料制造能力的需求情况,核电站产生的乏燃料量,分离钚产生量。乏燃料后处理能力作为我国核燃料循环体系的重要组成部分,将对我国核燃料循环情景产生重要影响。本文对后处理规模和分离钚的利用进行了假设,研究了两种情景模式下后处理和分离钚利用对我国铀资源需求和核废物产生的影响。     

分级方法在核燃料循环设施安全要求中的应用及相关标准浅析

核燃料循环设施类型多样,分级方法在核燃料循环设施中有较广的应用,标准在指导如何分级中发挥了重要作用。文章以IAEA安全标准第SSR-4《核燃料循环设施安全要求》的要求为参考,结合我国核燃料循环设施的安全相关标准要求,简要分析了分级方法在核燃料循环设施分类、物项安全分级、纵深防御等方面的应用,并提出了分级方法相关标准的建议。     

我国核燃料循环设施应对自然灾害采用标准现状分析及建议

自然灾害威胁核设施的安全,随着我国核燃料循环工程建设的迅速发展,探讨分析我国核燃料循环设施在设计、选址方面采用标准现状及存在的问题,制定相应的标准、规范以保证这些设施能够抵御自然灾害。     

核燃料循环“一次通过”情景分析研究

在我国大力发展核电和建立先进闭式燃料循环体系的前提下,为了核燃料循环各环节相互匹配,有机协调地发展核电,需对核燃料循环各环节的规模、布局等开展模拟分析研究。为了综合比较闭式燃料循环在铀资源利用率、环境友好型等方面的优势,还需对核燃料循环的"一次通过"方式进行分析研究。根据我国核电目前和中长期发展规划,假设2050年中国核电装机容量分别达到100GW、200GW和300GW,核电站全部采用压水堆,核燃料循环采用"一次通过"方式,利用简化模型,计算分析了近100年内累计需要的天然铀、每年需要的天然铀、每年需要的分离功、累计产生的乏燃料和需要离堆暂存的乏燃料量等关键数据。     

美国先进核燃料循环计划概述及对我国的启发

美国已重启核能计划,其中先进的核燃料循环计划是核能计划的核心。若这一计划得以顺利实施,将可以消除人们曾担忧的核能开发中的三大问题,核扩散、高放废物的处置和铀资源的可持续性问题。美国这一计划对我国的核能发展应有一些启发。     

The case for the fusion hybrid

The use of nuclear fusion to produce fuel for nuclear fission power stations is discussed in the context of a crucial need for future energy options. The fusion hybrid is first considered as an element in the future of nuclear fission power to provide long term assurance of adequate fuel supplies for both breeder and convertor reactors. Generic differences in neutronic characteristics lead to a fuel production potential of fusion-fission hybrid systems which is significantly greater than that obtainable with fission systems alone. Furthermore, cost benefit studies show a variety of scenarios in which the hybrid offers sufficient potential to justify development costs ranging in the tens of billions of dollars. The hybrid is then considered as an element in the ultimate development of fusion electric power. The hybrid offers a near term application of fusion where experience with the requisite technologies can be derived as a vital step in mapping a credible route to eventual commercial feasibility of pure fusion systems. Finally, the criteria for assessment of future energy options are discussed with prime emphasis on the need for rational comparison of alternatives. This approach is contrasted with the dual standard too often used in judging the risks and benefits of nuclear power where, for example, rather minor radiological effects are highlighted while much larger exposures to radiation from medical x-rays, airplane travel, color television sets, etc., are ignored. It is concluded that the fusion hybrid deserves a prominent place among new energy resources but that early attention to insure an adequately informed public is a vital ingredient in assuring reasonable prospects of success.     

质谱学在核科学技术中的应用概况及其展望

评述了质谱学在核科学技术中的应用概况。重点阐述了在核燃料工业、核反应堆工业和核数据测量中的应用，并对今后发展提出了看法。     

压水堆核燃料组件价格形成及对核发电成本的影响初探

从分析核燃料组件价格的形成入手,讨论了核燃料组件价格的形成特点及其对核发电成本的影响。     

2020年前我国核燃料循环情景初步研究

根据我国核电现状和中短期发展规划,对2020年前我国核电规模提出了三种预测方案,并根据各种方案对压水堆电站的核燃料循环情景进行了计算。重点研究了压水堆核电所需的铀资源、分离功,卸出的乏燃料以及乏燃料中Pu和次要锕系元素(MA)的产生量。     

Additional studies of criticality safety of failed used nuclear fuel

Commercial used nuclear fuel (UNF) in the USA is expected to remain in storage for periods potentially greater than 40 years. Extended storage (ES) time and irradiation to high burnup values (>45 GWd t^?1) may increase the potential for fuel failure during normal and accident conditions involving storage and transportation. Fuel failure, depending on the severity, could result in changes to the geometric configuration of the fuel, which has safety and regulatory implications. The likelihood and extent of fuel reconfiguration and its impact on the safety of the UNF are not well understood. The objective of this work is to assess and quantify the impact of fuel reconfiguration due to fuel failure on the criticality safety of UNF in storage and transportation casks. Criticality analyses are conducted considering representative UNF designs covering a range of enrichments and burnups in multiple cask systems. Prior work developed a set of failed fuel configuration categories, and specific configurations were evaluated to understand trends and quantify the consequences of worst case potential reconfiguration progressions. These results are summarised here and indicate that the potential impacts on subcriticality can be rather significant for certain configurations (e.g. >20% Δk_eff). However, for credible fuel failure configurations from ES or transportation following ES, the consequences are judged to be manageable (e.g. <5% Δk_eff). The current work expands on the previous efforts by including part length rods in fresh boiling water reactor fuel assemblies and studying the effect of damage in varying numbers of fuel assemblies.     

Inert matrix fuel for the utilisation of plutonium

Utilising fuel resources responsibly, reducing waste volume and emissions as well as conflict potentials within the international community (non-proliferation, energy demand) are among the principles for the judgment of sustainable development. Utilising and burning plutonium in a light water reactor has been shown to be feasible for the disposition of the large amount of excess plutonium produced in today's power reactors and resulting from the disarmament efforts of the super powers. With regard to material technology aspects, efforts have concentrated on the evaluation of fabrication feasibility and on the determination of the physicochemical properties of a single phase zirconium/erbium/plutonium oxide material stabilised as a cubic solution by yttrium for plutonium and minor actinide incineration and transmutation. Due to the absence of uranium as origin for plutonium build-up, such a nuclear fuel is called Inert Matrix Fuel. Irradiation testing with a dedicated experiment in the material test reactor in Halden, Norway, is underway within the framework of the OECD-Halden Reactor Project.     

我国乏燃料后处理大厂建设的几点思考

本文在分析了国际乏燃料后处理设计思路、工艺流程、相关关键技术、建造过程和运营经验的基础上,结合我国乏燃料后处理技术现状以及相关配套,就我国乏燃料后处理大厂的建设提出初步的思考.     

加速器驱动先进核能系统的乏燃料循环再生研究北大核心CSCD

乏燃料后处理是核燃料循环的关键环节,制约核电的可持续发展。借助于加速器驱动先进核能系统(ADANES)提供的高通量、硬能谱的外源中子,其乏燃料后处理只需除去乏燃料中的挥发性裂变产物和影响次锕系元素嬗变的中子毒物,长寿命的次锕系元素Np、Am、Cm可与二氧化铀一起转化为新的燃料元件在加速器驱动燃烧器中燃烧、嬗变、增殖和产能。基于此,本课题组提出了加速器驱动的乏燃料后处理及再生制备的技术路线,包括高温氧化粉化与挥发、选择性溶解分离和燃料再生制备。本文主要介绍了近几年本课题组在这三方面所取得的一些成就,希望能为加速器驱动先进核能系统的乏燃料后处理提供基础数据。     

田湾核电厂铀钆燃料管理的主要安全问题

本文针对田湾核电厂铀-钆燃料的燃料管理策略,探讨了相关的主要安全问题。它主要包括燃料管理论证的范围、铀-钆燃料芯块熔化温度的限值、相关的事故分析以及铀-钆燃料设计运行经验。最后指出了对我国压水堆核电厂燃料管理的经验反馈。