Optimization of the Technical and Economic Performance Indicators of Nuclear Power Plants with Fast Reactors

The results of design analyses for improving nuclear plants with fast reactors, specifically, by using cartridge-vessel generators instead of sectional-modular generators, are presented. It is shown for a nuclear power plant with a BN-800 reactor that the cartridge-vessel steam generators designed by the Special Machine Design Office substantially decrease the metal content, dimensions, mass, amount of construction work, and construction costs of the main vessel of the nuclear power plant.In the BN-800 design, a cartridge-vessel steam generator decreases the specific capital costs for constructing a power-generating unit of a nuclear power plant by approximately 8%, which substantially closes the gap between these costs for nuclear power plnats with BN-800 and VVER-1000 reactors.__________Translated from Atomnaya Energiya, Vol. 98, No. 6, pp. 403–412, June 2005.     

核电厂土建施工三大原材料质量控制

核电厂的建造运行是一项系统工程。为了保证核电厂的质量安全,从设计立项到运行使用,每一个环节的工作都对质量安全产生不同程度影响。与之相关的每一步工作都必须做到质量受控。从核电厂建造过程中土建施工环节中的原材料质量控制入手,着重分析了土建施工中钢材、混凝土材料、模板材料三大主材如何实施质量控制和管理。     

Economic potential of modular reactor nuclear power plants based on the Chinese HTR-PM project

Modular reactors with improved safety features have been developed after the Three-Mile Island accident. Economics of small modular reactors compared to large light water reactors whose power output is 10 times higher is the major issue for these kind of reactors to be introduced into the market. Based on the Chinese high temperature gas-cooled reactor pebble-bed module (HTR-PM) project, this paper analyzes economical potentials of modular reactor nuclear power plants. The reactor plant equipments are divided into 6 categories such as RPV and reactor internals, other NSSS components and so on. The economic impact of these equipments is analyzed. It is found that the major difference between an HTR-PM plant and a PWR is the capital costs of the RPV and the reactor internals. The fact, however, that RPV and reactor internals costs account for only 2% of the total plant costs in PWR plants demonstrates the limited influence of this difference. On the premise of multiple NSSS modules forming a nuclear power plant with a plant capacity equivalent to a typical PWR plant, an upper value and a target value of the total plant capital costs are estimated. A comparison is made for two design proposals of the Chinese HTR-PM project. It is estimated that the specific costs of a ready-to-build 2 × 250 MW_th modular plant will be only 5% higher than the specific costs of one 458 MW_th plant. When considering the technical uncertainties of the latter, a 2 × 250 MW_th modular plant seems to be more attractive. Finally, four main points are listed for MHTGRs to achieve economic viability.     

核电厂建设的特点

阐述了核电厂建设与常规火电厂的最大不同 ,在于其严格的安全与质量要求以及更需要加强控制的建设进度与投资 ,使得项目管理及质量保证制度特别重要。对发展中国家来说 ,目前只有通过设计的自主化和设备的国产化来提高核电的经济性。并介绍了模块化施工方式及使设计与施工进一步密切结合以降低建造成本的可能。     

Economic aspects of the development of nuclear power and fuel cycle plants in the USSR

Conclusion Plutonium breeding in fast reactors themselves will not have any significant effect in the next 20–25 years on growth rate of the capacity of nuclear power stations with fast reactors.The character of the distribution of the capital expenditures on nuclear power stations and on the fuel cycle shows that the bulk of the expenditures is spent on the construction of the nuclear power stations and only 20% on the development of the fuel-cycle plants. For this reason, greatest savings of capital expenditure are given by a reduction in the construction costs of nuclear power stations by means of improvements in the design and of the reactor and the thermal and mechanical equipment of the plant.In the fuel cycle the biggest economic effect is produced by measures that lead to a reduction in the specific consumption of natural uranium since the capital expenditure on the mining operations constitutes about one-half of the total capital expenditures on the fuel cycle. The natural uranium costs also make up roughly one-half of the fuel component of the cost of electricity generated by a nuclear power station. As the price of uranium rises, this fraction of costs will also increase.Translated from Atomnaya Énergiya, Vol. 43, No. 5, pp. 365–369, November, 1977.     

Trends in the developments of new pipe systems for power plants

The necessity to save costs for building nuclear power plants whilst maintaining the high standard of safety requirements led, in the Federal Republic of Germany, through an increase in the stability of specifications to standardisation. As a result, the costs and schedules for nuclear power plant piping systems, which represent a schedule critical and thus a cost critical part of the nuclear power plant construction, are controllable and steerable. The principle of a basic, safe design offers the nuclear piping industry also for the future the opportunity for increasing efficiency, provided that sufficient pre-planning is available to ensure an orderly execution of piping, and that the available potential of experience of the specialized companies is used.     

Methodologies for rapid evaluation of seismic demand levels in nuclear power plant structures

A methodology for rapid assessment of both acceleration spectral peak and “zero period acceleration” (ZPA) values for virtually any major structure in a nuclear power plant is presented. The methodology is based on spectral peak and ZPA amplification factors, developed from regression analyses of an analytical database. The developed amplification factors are applied to the plant's design ground spectrum to obtain amplified response parameters. A practical application of the methodology is presented.This paper also presents a methodology for calculating acceleration response spectrum curves at any number of desired damping ratios directly from a single known damping ratio spectrum. The methodology presented is particularly useful and directly applicable to older vintage nuclear power plant facilities (i.e. such as those affected by USI A-46). The methodology is based on principles of random vibration theory. The methodology has been implemented in a computer program (SPECGEN). SPECGEN results are compared with results obtained from time history analyses.     

基于和睦系统的ACPR1000核电机组保护系统优先级管理系统方案设计

通过梳理DI&C-ISG-04标准和ACPR1000核电机组对优先级管理系统（CIS）的功能要求，参考CPR1000核电机组CIS方案中的经验反馈，分析CIS设计中的诸多难点，提出了一套基于和睦系统（FirmSys）的ACPR1000核电机组保护系统CIS方案。相比CPR1000核电机组，ACPR1000核电机组的CIS方案采用了多种设计手段进行优化，如自主化和国产化设计、更优的防软件共因故障设计、更可靠的在线定期试验设计、模块化及多接口设计、就地功能设计。该设计方案已成功应用于ACPR1000核电机组，运转良好。因此本研究提出的CIS方案切实可行。      

SMR模块化运输带来的挑战

小型模块化反应堆(SMR)模块化的特点可以弥补大型核电厂建造周期长、资金压力大的缺点,且应用场景广泛,是当前各国核工业的研究热门。尽管有大量文献针对SMR的堆芯安全展开研究,但鲜有文献是关于SMR的运输安全。本文通过查阅文献并结合网上信息,从3个方面总结了SMR给运输安全领域带来的挑战,包括:大型重型模块运输、核燃料运输和装载燃料的密封堆芯运输,并给出了合理化建议。     

基于国产化PXI模块的松脱部件监测系统软件开发

基于国产化PXI（面向仪器系统的PCI扩展）模块,利用中国核动力研究设计院（NPIC）研制的国产化松脱部件监测系统（LPMS）进行了16通道LPMS软件的开发,本文主要介绍了软件设计要求、设计原则、设计流程,以及主界面的设计,并重点对国产化PXI控制模块接口程序的软件实现进行了详细阐述。开发的基于国产化PXI模块的LPMS软件经测试满足设计要求,并已成功应用在出口国外某核电厂的LPMS中,为保障核电厂安全经济的运行起到了积极的作用。      

Current status and technical description of Chinese 2 × 250 MWth HTR-PM demonstration plant

After the nuclear accidents of Three Mile Island and Chernobyl the world nuclear community made great efforts to increase research on nuclear reactors and to develop advanced nuclear power plants with much improved safety features. Following the successful construction and a most gratifying operation of the 10 MW_th high-temperature gas-cooled test reactor (HTR-10), the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University has developed and designed an HTR demonstration plant, called the HTR-PM (high-temperature-reactor pebble-bed module). The design, having jointly been carried out with industry partners from China and in collaboration of experts worldwide, closely follows the design principles of the HTR-10.Due to intensive engineering and R&D efforts since 2001, the basic design of the HTR-PM has been finished while all main technical features have been fixed. A Preliminary Safety Analysis Report (PSAR) has been compiled.The HTR-PM plant will consist of two nuclear steam supply system (NSSS), so called modules, each one comprising of a single zone 250 MW_th pebble-bed modular reactor and a steam generator. The two NSSS modules feed one steam turbine and generate an electric power of 210 MW.A pilot fuel production line will be built to fabricate 300,000 pebble fuel elements per year. This line is closely based on the technology of the HTR-10 fuel production line.The main goals of the project are two-fold. Firstly, the economic competitiveness of commercial HTR-PM plants shall be demonstrated. Secondly, it shall be shown that HTR-PM plants do not need accident management procedures and will not require any need for offsite emergency measures.According to the current schedule of the project the completion date of the demonstration plant will be around 2013. The reactor site has been evaluated and approved; the procurement of long-lead components has already been started.After the successful operation of the demonstration plant, commercial HTR-PM plants are expected to be built at the same site. These plants will comprise many NSSS modules and, correspondingly, a larger turbine.     

An extended value-impact approach for nuclear regulatory decision making

This paper presents an extended value-impact methodology which aids decision makers in ranking various alternative actions for reducing the risk associated with nuclear power reactors. It extends the state-of-the-art value-impact methodology by using the Analytic Hierarchy Process (AHP), a formalized decision making tool for ranking alternatives based on judgment. The AHP reduces some of the limitations present in current value-impact work, such as the inability to include subjective factors in a structured approach, as well as controversial questions such as the importance of onsite versus offsite accident costs averted, uncertainty, and impact of public opinion.In the paper, the method is applied to include a value-impact study of the implementation of either a vented-containment system or an alternative decay heat removal system as a means for reducing risk at the Grand Gulf nuclear power plant. The results of this analysis show that the method provides considerable insight to the solution of topics of interest in the decision making area of nuclear power risk management.     

AP1000的FCD混凝土浇筑时间管理研究及应用

海阳核电采用先进的第三代AP1000核电技术,其非能动系统设计理念,模块化及"开顶法"施工理念使建设周期大大缩短,同时对施工管理、质量及进度控制提出了更高的要求。将统计过程控制理论与方法应用于海阳AP1000核电1号机组FCD(First Concrete Day)混凝土浇筑时间管理过程中,通过模型建立、数据分析、模型优化并结合工程实际进行验证,提出了FCD时间管理的数学模型。本文研究的理论和方法不仅适用海阳AP1000核电1号机组FCD混凝土浇筑,而且对后续同类大体积混凝土连续浇筑具有借鉴和指导意义。     

SVBR-75/100 Multipurpose Modular Low-Power Fast Reactor with Lead–Bismuth Coolant

The results of development work on the SVBR-75/100 modular fast reactor cooled by lead–bismuth coolant are presented. The design is based on the experience gained operating reactors in nuclear-powered submarines. The SVBR-75/100 reactor is inherently safe because of its low power, the chemical inertness and high boiling point of the lead–bismuth coolant, and the integrated basin-type arrangement of the first-loop equipment. This eliminates the conflict between the safety and economic requirements that is characteristic of conventional-type reactors. The lower power makes it possible to build the reactor in a factory and deliver the reactor using any form of transportation to the nuclear power plant site. All safety systems operate passively. Most of these systems are used as normal-operating systems. This creates conditions for multipurpose applications of such reactor modules in developed and developing countries.     

Conceptual Design of a Modular Island Core Fast Breeder Reactor “RAPID-M”

A metal fueled modular island core sodium cooled fast breeder reactor concept RAPID-M to improve reactor performance and proliferation resistance and to accommodate various power requirements has been demonstrated. The essential feature of the RAPID-M concept is that the reactor core consists of integrated fuel assemblies (IFAs) instead of conventional fuel subassemblies. The RAPID concept enables quick and simplified refueling by replacing IFAs in which all the core and blanket fuel elements are comprised. In this paper, the 600 MWe RAPID-M design consists of 7 IFAs is presented. Significant reactor mass savings and the improvement of inherent safety features are discussed. Plant dynamics analyses using the multi-point reactor kinetics equations to accommodate the modular core configuration demonstrated a favorable transient response in case of unprotected transient over power (UTOP).     

核电厂辐射环境监督性监测系统选址和设计的思考和建议

本文基于某核电厂监督性监测系统建设的实践,同时参考其他核电厂的经验反馈对该系统选址和方案设计中容易疏忽以及需要关注的重点问题予以分析和讨论,提出相关建议,可供核电厂开展核电厂同类工作参考和借鉴。本文基于某核电厂监督性监测系统建设的实践,同时参考其他核电厂的经验反馈对该系统选址和方案设计中容易疏忽以及需要关注的重点问题予以分析和讨论,提出相关建议,可供核电厂开展核电厂同类工作参考和借鉴。     

A 10 MWe pressurized water reactor for safe and reliable power

A design for an innovative, passively safe 10 MWe power plant based on the proven pressurized water reactor technology has been developed. The plant incorporates an innovative design approach to achieve “walk-away” safety and includes significant simplification and elimination of systems and components when compared to the current generation commercial nuclear power plants. The plant has been designed such that the majority of the equipment will be pre-assembled as modules at off-site facilities and shipped to the site on trucks for installation. This approach will provide shorter construction schedules and improved quality control.     

The organic-cooled organic-moderated nuclear power station “ARBUS”

Summary The installation and the experimental operation of the ARBUS nuclear electric power generating station demonstrated the feasibility of constructing organic-cooled nuclear power stations in remote regions of the USSR. The correctness of the calculations and principal design decisions, the realizability of equipment fabrication and of the carbon steel primary-loop piping without any biological shielding, and the possibility of exploiting available mass-produced petrochemical equipment and standard fittings, giving due attention to the specific requirements of a nuclear facility, were confirmed in operation. This nuclear power station exhibits adequate operational stability, with the added advantages of simplicity and reliability in operation under a variety of operating conditions.In subsequent work, improvements can be made in the engineering costs of power stations of this type by increasing the process parameters (employing regenerable coolant of higher thermal stability), and by introducing other power plant improvements based on the accumulated operating experience.Translated from Atomnaya Énergiya, Vol. 17, No. 6, pp. 439–448, December, 1964     

部分参数统计方法在30万kW核电厂应用的初步研究

偏离泡核沸腾(DNB)设计基准是反应堆热工水力设计中的重要基准之一,为评价该设计基准是否满足热工水力设计要求,需确定堆芯偏离泡核沸腾比(DNBR)设计限值。本文研究了使用统计学方法确定不确定性的部分参数统计方法原理,并应用该方法和堆芯子通道分析程序对30万kW核电厂DNBR设计限值进行计算。计算结果表明,反应堆冷却剂流量全部丧失事故最小DNBR分析采用部分参数统计较STDP额外获得了约5%的裕量。本文结果为DNBR设计基准的验证提供了关键判据。