球床高温气冷堆核电站放射性废物最小化策略研究

放射性废物最小化是放射性废物管理的基本原则之一。高温气冷堆核电站放射性废物最小化策略研究对于优化设计与运行实践和全寿期放射性废物管理,以及高温气冷堆产业化发展具有重要意义。通过对世界上主要球床高温气冷堆运行历史和放射性废物数据的调研和论证,分析了球床高温气冷堆技术及其放射性废物特点,总结了高温气冷堆放射性废物管理值得借鉴经验及相关研究进展,提出了高温气冷堆核电站全寿期放射性废物最小化的策略和建议。     

高温气冷堆在我国应用的预可行性研究摘要

本文概述了高温气冷堆在我国核能发展中的地位和作用,并对国内应用高温气冷堆的市场做了初步调查和分析,同时,做了小型高温气冷堆核电站 HTR100 型的初步适应性设计和经济估算。结果表明,在我国建造小型高温堆核电站在技术上是可行的。在一些地区,其发电成本可与同规模的煤电厂相接近。     

模块式高温气冷堆的技术背景及展望

模块式高温气冷堆具有固有安全性、发电效率高、用途广泛等特点,是第四代核能系统代表堆型之一,也是我国16个重大科技专项之一。本文介绍了高温气冷堆的发展历史,对高温气冷堆国际研究现状进行了阐述,说明了高温气冷堆在我国的发展情况。介绍了我国正处于调试期的模块式高温气冷堆示范电站的技术特点,从高效发电、工艺热应用、能源替代、分布式能源四个角度对模块式高温气冷堆的发展前景进行了分析,提出了我国模块式高温气冷堆后续工作建议。     

我国高温气冷堆核电站的标准化建设

中国积极推进核电建设的战略方针对本国核电标准体系的建设提出了迫切的要求。在高温气冷堆核电站被列为国家中长期科技发展规划中的重大专项的背景下,文章以高温气冷堆技术为主体,在阐述高温气冷堆核电站标准化建设的意义和必要性的基础上,介绍了我国近期开展的高温气冷堆核电站标准体系的建立,以及后续工作的初步设想。     

高温气冷堆产业推广及应用前景

高温气冷堆是我国具有完全自主知识产权的第四代先进核能技术,具有固有安全性、模块化设计及建造、发电效率高、用途广泛等特点。文章介绍了高温气冷堆产业化推广以及高温气冷堆在替代中小火电、制氢、石化和海水淡化等领域多功能综合利用的发展前景,分析了高温气冷堆产业化面临的挑战,指明了高温气冷堆产业化发展的重要意义。     

法美俄日将合作开发小型核电站

【据因特网 1 999年 7月 7日报道】　目前 ,高温核反应堆在技术上已不存在太多障碍。法国法马通公司将与美国通用原子能公司、俄罗斯能源部及有关研究所、日本富士电力公司合作 ,运用模块式高温气冷堆技术开发 2 50 MW或 30 0 MW的新一代小型核电站。到 2 0 1 0年左右 ,不管是从技术上还是从经济上考虑 ,这种核电站将成为中型热能和电能生产单位的最佳选择 ,这是法马通公司主持的高温气冷堆国际研讨会得出的结论。模块式高温气冷堆的特点是将氦气同时作为核反应堆芯的冷却剂和驱动气轮机发电的动力 ,提高反应堆出口温度和热转换效率。这个…     

核电站堆型

随着核电站商业化和标准化进展,七十年代以来逐步形成了以已经商用的轻水堆、重水堆以及即将发展成为商用的高温气冷堆和快中子增殖堆为主要堆型。从核电装机容量统计,轻水堆的核发电量约占80％,其次是重水堆和气冷堆,纳冷快中子增殖堆虽然目前发电容量还     

裂变室探测器在高温气冷堆核电站示范工程核测量系统中的应用

高温气冷堆核电站示范工程是我国中长期发展规划中的重大专项之一,也是我国第一座拥有自主知识产权的核电站。文章介绍了高温气冷堆核电站核测量系统的工作原理和系统组成,剖析了裂变室中子探测器的特点及其在核测量系统中的应用。裂变式探测器所具有的γ信号甄别能力强、中子通量测量范围宽等优点,应用于高温气冷堆核测量系统,可以满足大空间、宽范围的堆外中子通量测量需求,有利于简化系统组成、提高经济性。与其他压水堆核电站的核测量系统相比较,应用裂变室中子探测器具有一定的优越性。     

模块式高温气冷堆核电站设计特点

模块式高温气冷堆具有安全、灵活、可靠、经济性好的优点,受到核技术先进国家的重视。本文着重介绍了美国新近推出的模块式高温气冷堆核电站的设计特点和安全特性。     

高温气冷堆技术的研究及发展

自1954年前苏联第一座SMW试验性核电站投运以来,核电在一些国家的电力工业中保持着重要作用。从世界核电下一阶段发展来看,重点仍是提高安全性和降低造价,主要发展的是先进的水堆技术和其他先进的反应堆技术,可以预测,高温气冷堆技术作为一种先进反应堆技术在未来的10～15年必将取得长足的发展。 高温气冷堆技术的发展和现状 气冷堆是国际上反应堆发展中最早的一种堆型,这种反应堆初期被用来生产军用钚,20世纪50年代中期以后发展成为商用核电站的堆型之一。气冷堆的发展大致可以分为四个阶段:即早期气冷堆(Magnox)、改进型气冷堆(AGR)、…     

美国高温气冷堆及其近期发展计划

简要地说明了美国高温气冷堆的发展过程,评价了美国已建成的高温气冷堆,介绍了美国目前正在实施的发展模块式高温气冷堆的三项计划。     

世界核电发展趋势与高温气冷堆

核能的发展面临经济竞争力、核安全、核废物的最终处置及防止核武器材料扩散的挑战。为改善公众的可接受性 ,核电厂的安全性进一步改进。电力市场体制的非管制化改革加剧了电力技术的竞争。环境保护意识增强使核废物的处置倍受关注。 80年代中期以来发展的先进轻水堆核电厂如ABWR ,System 80 ,EPR ,AP60 0等是今后一段时期内商用核电的主力堆型。进入 2 0 0 0年之际 ,美国能源部正在规划发展第四代先进核能系统 ,目标是在 2 0 2 0年或之前 ,向市场提供经过验证的成熟的第四代核电厂技术 ,以替代美国退役的核电容量。球床高温气冷堆被认为是第四代先进核能系统的优选技术。南非ESKOM电力公司选择了球床高温气冷堆作为今后核电发展的堆型。清华大学承担设计和建设的 10MW高温气冷实验堆计划在 2 0 0 0年内临界。通过10MW高温气冷堆的建造 ,我国已形成了高温气冷堆技术的自主知识产权 ,初步具备了自主设计、制造和建造的能力     

Reactor units developed by OKBM Afrikantov for low- and medium-capacity nuclear power plants

A system of requirements for low- and medium-capacity nuclear power-generating units with guaranteed market demand is presented. OKBM Afrikantov has developed designs for reactor units for low- and medium-capacity nuclear power plants that can be used as power sources in floating nuclear power plants for supplying heat and power in remote regions in the coastal zone, power-generating units as components of nuclear water desalination complexes and for supplying power for marine oil drilling platforms, stationary nuclear power plants for supplying heat and power in separate regions, large industrial enterprises, and cities. ABV, KLT, RITM, VBER, and HTGR reactor units for power sources of this type are reviewed and their characteristic features as well as those of nuclear power plants based on them are indicated.     

球床式高温气冷堆的余热不确定性分析

反应堆在停堆后相当长时间内仍具有较高的剩余发热是核电站的重要特性,也是核电站安全分析的关键。因此,对反应堆余热及其不确定性进行分析,对于合理设计余热排出系统、研究论证燃料元件在事故后的安全特性等均具有重要意义。本工作结合德国针对球床式高温气冷堆制定的余热计算标准,介绍了球床式高温气冷堆剩余发热及其不确定性的计算方法,并结合200 MWe球床模块式高温气冷堆示范工程（HTR-PM）的初步物理设计,对长期运行在满功率平衡堆芯状态下的反应堆停堆后的余热及其不确定性进行了计算分析,为进一步的事故分析提供依据。     

Future HTGR developments in China after the criticality of the HTR-10

Nuclear power has a great potential to develop in China because of China's fast economic increase. HTGR will be the most promising nuclear reactor to apply in the future Chinese market. After the initial criticality of the HTR-10, subsequent research and validation of the HTGR performance is by hot commissioning tests and power operation, safety demonstration experiments, R&D of gas turbine and process heat application technologies, and promotion of industrial application of HTGR technologies. The commercial prototype HTR-PM is under study and conceptual design has started. These activities will result in the safe and economic development of HTGR technologies in China.     

The HTGR gas turbine plant with dry air cooling

The development of the HTGR gas turbine power plant as a future evolution of the HTGR is one of the most promising solutions to the interrelated power generation and environmental problems. The HTGR gas turbine can make dry air cooling economical and can make possible increased flexibility and economy in power plant siting. The simplification and size reduction of the overall plant imply lower capital costs. Cycle parameters and plant layout for a typical HTGR direct-cycle gas turbine plant of 1100 MW(e) output are described. For safety reasons all the primary equipment is integrated inside the prestressed concrete reactor vessel. Four parallel loops are contained in eight vertical PCRV cavities located around the core cavity. Alternative design configurations and parameter choices are discussed. The advantages and the development potential of the direct cycle with regard to heat rejection and cost are discussed. The possibility of profitably using the gas turbine thermal discharge for operating a seawater distillation plant is pointed out.     

Digital Simulaiion of a Commercial Scale High Temperature Gas-Cooled Reactor (HTGR) Steam Power Plant

A nonlinear dynamic model of a commercial scale high temperature gas-cooled reactor (HTGR) steam power plant was derived in state-space form from fundamental principles. The plant model is 40th order, time-invariant, deterministic and continuous-time. Numerical results were obtained by digital simulation. Steady-state performance of the nonlinear model was verified with plant heat balance data at 100, 75 and 50 percent load levels. Local stability, controllability and observability were examined in this range using standard linear algorithms. Transfer function matrices for the linearized models were also obtained. Transient response characteristics of 6 system variables for independent step disturbances in 2 different input variables are presented as typical results. Simulation of the HTGR steam power plant provides the basis for (a) understanding the complex and highly interactive process dynamics, (b) designing an interactive multivariable controller, and (c) studying plant dynamic performance under various operating and upset conditions. Modeling and simulation techniques developed in the work from which this paper is abstracted have general applicability, and can be readily adapted to the study of gas-cooled steam power plants.     

HTGR plant safety design bases

The high temperature gas-cooled reactor (HTGR) has inherent and design safety features that are sifnificant and unique, requiring a number of safety criteria and approaches that differ markedly from other reactor types. This paper briefly reviews the design of HTGR plants that have been built and are being offered in the United States. It then reviews the safety considerations involved in the design of the plants being offered. The unique features, their development, and their effects on safety criteria are described. The design bases of the prestressed concrete reactor vessel (PCRV) are given particular attention. Operating characteristics of the HTGR and plant response to transient conditions are discussed. The design-basis depressurization accident evolution and related HTGR safety requirements are discussed. Characteristics of the HTGR with respect to technical specifications are discussed, with particular emphasis on the PCRV and the core safety limit.     

HTGR reactor physics and fuel cycle studies

The high-temperature gas-cooled reactor (HTGR) appears as a good candidate for the next generation of nuclear power plants. In the “HTR-N” project of the European Union Fifth Framework Program, analyses have been performed on a number of conceptual HTGR designs, derived from reference pebble-bed and hexagonal block-type HTGR types. It is shown that several HTGR concepts are quite promising as systems for the incineration of plutonium and possibly minor actinides.These studies were mainly concerned with the investigation and intercomparison of the plutonium and actinide burning capabilities of a number of HTGR concepts and associated fuel cycles, with emphasis on the use of civil plutonium from spent LWR uranium fuel (first generation Pu) and from spent LWR MOX fuel (second generation Pu). Besides, the “HTR-N” project also included activities concerning the validation of computational tools and the qualification of models. Indeed, it is essential that validated analytical tools are available in the European nuclear community to perform conceptual design studies, industrial calculations (reload calculations and the associated core follow), safety analyses for licensing, etc., for new fuel cycles aiming at plutonium and minor actinide (MA) incineration/transmutation without multi-reprocessing of the discharged fuel.These validation and qualification activities have been centred round the two HTGR systems currently in operation, viz. the HTR-10 and the HTTR. The re-calculation of the HTTR first criticality with a Monte Carlo neutron transport code now yields acceptable correspondence with experimental data. Also calculations by 3D diffusion theory codes yield acceptable results. Special attention, however, has to be given to the modelling of neutron streaming effects. For the HTR-10 the analyses focused on first criticality, temperature coefficients and control rod worth. Also in these studies a good correspondence between calculation and experiment is observed for the 3D diffusion theory codes.     

安全经济高效的先进能源

具有第四代安全经济特性的核电应该是人们期待的先进的清洁低碳能源。高温气冷堆是当今研发的第四代核电堆型之一,但现有的设计还存在需要排除的严重的安全隐患。堆芯不熔化,不等于说不会有严重事故发生。需要吸取国外球床高温堆和柱状高温堆两种实验堆型运行的经验教训、扩展安全观念和应对安全低概率事件,确保反应堆不出现后果极其严重的放射性释放事故。当热电转换系统采用与燃气蒸汽联合循环耦合应用的技术以后,会发挥高温堆所长,更大地提升转换效率,形成一种高安全低投资和高效率的双燃料清洁能源,可用于大堆或小堆的应用环境,可满足电力系统基本负荷和调锋负荷的需要。在工程设计上采取一系列改进和创新措施,包括釆用规则床模块化及地下反应堆设计以后,可在提高反应堆核心部位安全防卫能力的同时,防范低概率事件,成为一种新的安全经济高效的先进能源。