铅冷快堆M2LFR-1000堆芯燃料管理方案设计

堆芯燃料管理是反应堆设计中极为重要而且复杂的工作,直接影响着堆芯的经济性。目前国内外对于压水堆等传统热堆已有了较为丰富和成熟的燃料管理计算方法,但对于快堆,由于其中子能谱硬,与传统热堆相比有着不同的控制方式和功率分布,快堆的堆芯燃料管理缺乏系统研究。针对中国科学技术大学自主研发的强迫循环冷却的铅基快堆M2LFR-1000,应用SRAC/COREBN软件包进行堆芯燃耗计算,根据燃耗深度提取核素核子密度,计算伪平衡循环参数进行燃料管理预估,然后进行首循环装料、过渡循环和平衡循环燃料管理方案设计。结果表明:对M2LFR-1000堆芯外区燃料换料组件Pu的富集度进行优化,可以延长换料周期到540 d,提高平均卸料燃耗深度;伪平衡循环结果与平衡循环基本一致,伪平衡循环可以用于燃料管理预估。     

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使用Jsolver程序及托卡马克模拟程序TSC对紧凑型聚变裂变混合堆系统的反剪切平衡位形、自举电流份额及放电模拟进行数值模拟研究,以此探讨该混合堆的可行性和先进性.     

共生聚变堆

本文提出一种以发展聚变动力为主的共生式途径。它以当前正在出现的这一代聚变物理试验堆为起点,分成两路进行,一路是纯聚变堆,另一路是单个的氘发生器,可能是聚变裂变混合堆,它给纯聚变堆补充所需的氘。这两类堆长期结合共生,配合发展.形成一系需氚的纯聚变堆和一系供氚的混合堆,统一优化,保持氚自给,消耗氘锂和快中子裂变材料,提供净输出功率。 对纯聚变堆方面,放弃了传统的氚自给这一基本要求。能量的有效回收成为设计:的主要前提。优化的结果,用12—15厘米厚的含锂的水作为中子慢化回收能量的介质,附带地还能再生所耗氚的80％。不足的20％稍多的氚,将长期地由一个具有低Q聚变芯并依照生产氚的要求来改型并优化的一比一聚变裂变堆来补充。共生的两个堆,尺寸都较小,在等离子体物理和工程上有一些优点。对共生堆和具有相等总输出功率的,一般氚自给聚变堆作了比较,表明在动力经济上有相当大的收益。 简单地讨论了几种有关的概念。     

聚变-裂变混合堆──中国发展增殖堆的道路

核能是21世纪的替代能源,远期靠聚变能,前期靠裂变能.地球上天然铀储量不多,必须充分利用丰产核238U和232Th.裂变增殖堆(快堆)和聚变增殖堆(聚变-裂变混合堆)是利用238U和232Th的两条主要途径. 聚变-裂变混合堆概念早在五十年代初就已提出[1].1960年,英国J.W.Weale的DT中子在天然铀铀柱中的宏观实验[2],为混合堆奠定了实验基础.六十年代开展了大量混合堆包层中子学理论和实验研究.1965年美国L.N.Loutai第一个提出融盐增殖包层的概念设计[3].1969年美国 L.M.Lidsky第一个提出“混合堆-裂变堆共生系统”概念[4].1972年美国J.D.Lee第一…     

紧凑型聚变裂变混合堆自举电流的数值模拟研究

以平衡程序Jsolver 为基础开展了紧凑型聚变裂变混合堆先进等离子体平衡位形设计,重点研究了反剪切运行模式,并在此位形下研究了自举电流的计算、分布及份额。     

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以平衡程序Jsolver 为基础开展了紧凑型聚变裂变混合堆先进等离子体平衡位形设计,重点研究了反剪切运行模式,并在此位形下研究了自举电流的计算、分布及份额。     

次临界能源堆物理设计进展

聚变-裂变混合能源堆包括聚变中子源和次临界能源堆,主要目标是生产电能。回顾了国内外混合堆的发展历史,给出混合能源堆设计的边界条件和约束条件,说明次临界能源堆以铀锆合金为燃料、水为冷却剂的设计思想。利用输运燃耗耦合程序MCORGS计算了混合能源的燃耗,给出了中子有效增殖因数、能量放大倍数和氚增殖比等物理量随时间的变化。通过分析能谱和重要核素随燃耗时间的变化,说明混合能源堆与核燃料增殖、核废料嬗变混合堆的不同特点。论述了混合堆的热工设计并进行了安全分析。对于燃耗数值模拟程序,通过多家对算,保证其计算结果的可信性。针对次临界能源堆的特点,利用贫铀球壳建立了贫铀聚乙烯装置和贫铀LiH装置,并且专门设计加工了天然铀装置,开展铀裂变率、造钚率、产氚率等中子学积分实验,验证了数值模拟的可靠性。     

不同燃料循环方案的可持续性与经济性分析

基于核燃料循环政策技术的成熟度,选取了一次通过循环方案(OTC)、单次复用循环方案(TTC)、快堆闭式循环方案(FRC)及混合堆闭式循环方案(HRC)四种典型的核燃料循环方案进行分析。采用平衡物质流模型对不同燃料循环方案的可持续性进行研究,基于平准化电力成本计算方法对不同方案的燃料成本和乏燃料处置成本进行分析。研究结果表明:闭式燃料循环可极大减少核废料产生; 燃料可自持的FRC方案及HRC方案可使用贫铀做燃料而不消耗天然铀; 仅考虑燃料成本和乏燃料处置成本时,HRC方案的经济性最高而TTC方案的经济性最差。     

我国核能的现状和前景

国民经济的发展及人口的增长，使我国对能源的需求与日俱增．本文从资源、技术、经济及环境影响出发，论述了我国煤、石油、天然气、水能、太阳能、风能和核能的发展现状和前景，认为开发核能是解决我国能源、环境和交通问题的根本出路． 当前，压水堆是我国核电的主要堆型．在目前及今后一段时期，核电是我国利用核能的主要方向．到下世纪，能增殖核燃料的快堆将成为我国的主要堆型．我国的快堆开发，要走金属型核燃料快堆的道路．快堆使人类有充裕的时间，去迎接聚变堆时代的到来．     

紧凑型聚变裂变混合堆参数优化及放电模拟

在聚变裂变混合堆大、小半径分别不变情况下,通过优化聚变裂变混合堆中心螺管尺寸,用聚变系统分析程序对紧凑型聚变裂变混合堆的参数进行了优化分析,给出了紧凑型聚变裂变混合堆的最佳设计点。利用TSC平衡演化程序以该设计点为基础进行了放电模拟研究,结果表明该堆具有良好的经济优势及可行性。     

Variants of Regenerated Fissile Materials Usage in Thermal Reactors as the First Stage of Fuel Cycle Closing

At present, 240 000 t of spent nuclear fuel (SF) has been accumulated in the world. Its long-term storage should meet safety conditions and requires noticeable finances, which grow every year. Obviously, this situation cannot exist for a long time; in the end, it will require a final decision. At present, several variants of solution of the problem of SF management are considered. Since most of the operating reactors and those under construction are thermal reactors, it is reasonable to assume that the structure of the nuclear power industry in the near and medium-term future will be unchanged, and it will be necessary to utilize plutonium in thermal reactors. In this study, different strategies of SF management are compared: open fuel cycle with long-term SF storage, closed fuel cycle with MOX fuel usage in thermal reactors and subsequent long-term storage of SF from MOX fuel, and closed fuel cycle in thermal reactors with heterogeneous fuel arrangement. The concept of heterogeneous fuel arrangement is considered in detail. While in the case of traditional fuel it is necessary to reprocess the whole amount of spent fuel, in the case of heterogeneous arrangement, it is possible to separate plutonium and ²³⁸U in different fuel rods. In this case, it is possible to achieve nearly complete burning of fissile isotopes of plutonium in fuel rods loaded with plutonium. These fuel rods with burned plutonium can be buried after cooling without reprocessing. They would contain just several percent of initially loaded plutonium, mainly even isotopes. Fuel rods with ²³⁸U alone should be reprocessed in the usual way.     

Prospects for and problems of using light-water supercritical-pressure coolant in nuclear reactors in order to increase the efficiency of the nuclear fuel cycle

Trends in the development of the power sector of the Russian and world power industries both at present time and in the near future are analyzed. Trends in the rise of prices for reserves of fossil and nuclear fuels used for electricity production are compared. An analysis of the competitiveness of electricity production at nuclear power plants as compared to the competitiveness of electricity produced at coal-fired and natural-gas-fired thermal power plants is performed. The efficiency of the open nuclear fuel cycle and various versions of the closed nuclear fuel cycle is discussed. The requirements on light-water reactors under the scenario of dynamic development of the nuclear power industry in Russia are determined. Results of analyzing the efficiency of fuel utilization for various versions of vessel-type light-water reactors with supercritical coolant are given. Advantages and problems of reactors with supercritical-pressure water are listed.     

Advantages of Production of New Fissionable Nuclides for the Nuclear Power Industry in Hybrid Fusion-Fission Reactors

A concept of a large-scale nuclear power engineering system equipped with fusion and fission reactors is presented. The reactors have a joint fuel cycle, which imposes the lowest risk of the radiation impact on the environment. The formation of such a system is considered within the framework of the evolution of the current nuclear power industry with the dominance of thermal reactors, gradual transition to the thorium fuel cycle, and integration into the system of the hybrid fusion-fission reactors for breeding nuclear fuel for fission reactors. Such evolution of the nuclear power engineering system will allow preservation of the existing structure with the dominance of thermal reactors, enable the reprocessing of the spent nuclear fuel (SNF) with low burnup, and prevent the dangerous accumulation of minor actinides. The proposed structure of the nuclear power engineering system minimizes the risk of radioactive contamination of the environment and the SNF reprocessing facilities, decreasing it by more than one order of magnitude in comparison with the proposed scheme of closing the uranium–plutonium fuel cycle based on the reprocessing of SNF with high burnup from fast reactors.     

给水加热型联合循环的变工况性能

在联合循环改造的各种方案中,给水加热型具有投资少、改动少、耗用优质燃料较少、尤其是简单易行及技术难度小等特点,因此在我国现有的技术经济水平、特别是以煤为主的国情下,有一定应用市场。本文分析比较了多种变工况运行方式的性能及可能出现的问题,并在此基础上提出综合性能较好的运行模式。     

On the role of fusion neutron source with thorium blanket in forming the nuclide composition of the nuclear fuel cycle of the Russian Federation

The possible role of available thorium resources of the Russian Federation in utilization of thorium in the closed (U–Pu)-fuel cycle of nuclear power is considered. The efficiency of application of fusion neutron sources with thorium blanket for economical use of available thorium resources is demonstrated. The objective of this study is the search for a solution of such major tasks of nuclear power as reduction of the amount of front-end operations in the nuclear fuel cycle and enhancement of its protection against uncontrolled proliferation of fissile materials with the smallest possible alterations in the fuel cycle. The earlier results are analyzed, new information on the amount of thorium resources of the Russian Federation is used, and additional estimates are made. The following basic results obtained on the basis of the assumption of involving fusion reactors with Th-blanket in future nuclear power for generation of the light uranium fraction ^232+233+234U and ²³¹Pa are formulated. (1) The fuel cycle would shift from fissile ²³⁵U to ²³³U, which is more attractive for thermal power reactors. (2) The light uranium fraction is the most “protected” in the uranium fuel component, and being mixed with regenerated uranium, it would become reduced-enrichment uranium fuel, which would relieve the problem of nonproliferation of the fissile material. (3) The addition of ²³¹Pa into the fuel would stabilize its neutron-multiplying properties, thus making it possible to implement a long fuel residence time and, as a consequence, increase the export potential of the whole nuclear power technology. (4) The available thorium resource in the vicinity of Krasnoufimsk is sufficient for operation of the large-scale nuclear power industry of the Russian Federation with an electric power of 70 GW for more than one quarter of a century. The general conclusion is that involvement of a small number of fusion reactors with Th-blanket in the future nuclear power industry of the Russian Federation would to a large extent solve its problems and increase its export potential.     

Solid oxide fuel cell technology development in the U.S.

The U.S. Department of Energy (DOE) Office of Fossil Energy (FE) through the National Energy Technology Laboratory (NETL) is leading the development and demonstration of high efficiency and low cost solid oxide fuel cells (SOFCs) and fuel cell turbine (FCT) hybrid power generation systems primarily under the Solid State Energy Conversion Alliance (SECA). Additional long-term basic research is performed at the High Temperature Electrochemistry Center (HiTEC). Distributed generation (DG) systems have ultra low emissions, produce water, and can be configured to isolate/segregate carbon dioxide – all features useable in FutureGen and advanced coal-based systems.     

大型先进压水堆中次锕系核素嬗变特性

随着核电事业的快速发展,核电厂卸载的乏燃料越来越多。如何处置核电站乏燃料中的次锕系核素（MA）既是核燃料再利用的重要过程,又是闭式循环中的关键步骤。如果处置得当,不仅可以提高燃料的利用率,而且可以将MA变成同位素燃料电池、中子源等有用的核素。国际上认可的处置方法是分离-嬗变,但是嬗变MA的难点是嬗变堆型的选取和如何提高嬗变率。压水堆(PWR)是国内外最成熟的堆型和商业运行的主要堆型,也是现阶段最具有可能进行MA嬗变的堆型。于是,本文利用MCNP程序研究了压水堆嬗变MA的特性,通过研究MA嬗变棒的设计、添加位置和添加量等对压水堆堆芯有效增殖因子的影响,初步探索出最佳的压水堆嬗变MA的设计方案,为我国现阶段进行压水堆嬗变MA奠定了理论基础。     

The thorium cycle for fast breeder reactors

The role that could be played by liquid metal-cooled fast breeder reactors (LMFBRs) in the utilization of India’s considerable thorium resources is reviewed in this article. Distinct advantages of thorium-based fuels over plutonium-uranium fuels in LMFBRs pertain to a more favourable coolant voiding reactivity coefficient and better fuel element irradiation stability. The poorer breeding capability of thorium-fuelled fast reactors can in principle be overcome by improved core design and development of advanced fuel concepts. The technical feasibility of such advanced thorium fuels and core designs must be established by sustained research and development. It is also necessary to efficiently close the thorium fuel cycle of fast breeder reactors by appropriate development of the fuel reprocessing and refabrication stages. The Fast Breeder Test Reactor (FBTR) at Kalpakkam is expected to be an important tool for development of thorium fuel and fuel cycle technology. A quick look at the economics of the thorium cycle for fast reactors, vis-a-vis the more conventional uranium cycle indicates only a small and acceptable cost disadvantage on account of the need for remote fabrication of recycled thorium fuel. The authors felicitate Prof. D S Kothari on his eightieth birthday and dedicate this paper to him on this occasion.     

Z箍缩驱动聚变-裂变混合堆总体概念研究进展

Z箍缩驱动聚变-裂变混合能源堆(Z-FFR)在核安全、经济、持久和环境友好等方面具有优良的品质,有望成为有效应对未来能源危机和环境、气候问题的新能源。从Z箍缩驱动聚变方案与聚变靶设计、重复频率驱动器、次临界包层及产氚包层设计、燃料循环等关键问题方面,对Z-FFR工程概念总体研究情况进行了介绍。     

核电站乏燃料对生物圈的影响及ADS 对策

介绍了核电发展状况和核电产生的乏燃料中的锕系及长寿命裂变产物核素, 在毒性方面评述了这些核素对生物圈的影响, 最后提出用加速器驱动的次临界系统嬗变核废物的对策, 以减轻或消除核废物对生物圈的影响。 The current status of nuclear power development and the actinides and some Long Lived Fission Products (LLFPs) in nuclear power spent fuel have been introduced. The radiation effect of spent fuel on biological circle in the viewpoint of Biological Hazard Potential (BHP) and Annual Limit of Intake were evaluated. The Accelerator Driven Sub critical System （ADS） as a strategy to transmute Minor Actinides (MAs) and LLFPs was recommended in order to reduce or eliminate the radiation effect of spent fuel on biological circle.