一种低温堆核电站的动态数学模型

针对研发的采用一体化布置、全功率自然循环的低温核反应堆电站,建立了一个可用于大功率运行范围控制系统仿真的动态数学模型.模型采用了六组缓发中子动态方程(考虑了慢化剂温度和燃料温度反应性负反馈)、集中参数的堆芯传热模型以及自然循环流动模型,重点考虑了主回路自然循环对堆芯内冷却剂和燃料棒之间的传热系数、主换热器换热系数、主回路时间常数的影响.仿真结果表明,模型能够正确反映低温堆核电站的主要动态特性,可用于电站控制系统仿真.     

Single-loop nuclear power plant with a pressurized-water reactor

Trust Tsentroénergomontazh. Translated from Atomnaya Énergiya, Vol. 71, No. 5, pp. 458–460, November, 1991.     

Time-optimal control of nuclear reactor power with adaptiveproportional-integral-feedforward gains

A time-optimal control method which consists of coarse and fine control stages is described. During the coarse control stage, the maximum control effort (time-optimal) is used to direct the system toward the switching boundary, which is set near the desired power level. At this boundary, the controller is switched to the fine control stage in which an adaptive proportional-integral-feedforward controller is used to compensate for any unmodeled reactivity feedback effects. This fine control is also introduced to obtain a constructive method for determining the (adaptive) feedback gains against the sampling effect. The feedforward control term is included to suppress the over- or undershoot. The estimation and feedback of the temperature-induced reactivity are also discussed     

自动数字显示的反应堆核功率测量装置

介绍一种自动数字显示的反应堆核功率测量装置的工作原理,设计特点以及主要技术性能。     

Trends in nuclear power reactor design and technology

The continuing worldwide growth in energy consumption, in particular for electricity generation, coupled with increasing concerns regarding the environmental impact of the burning of fossil fuels, demands that nuclear power continue to be available as an option for generation electricity.However, nuclear power has not attained previously expected levels of deployment due to its own set of concerns including, primarily, poor performance and public acceptance of adequate safety. The lessons learned from the past experience are being carefully considered in the ongoing development programmes leading to advanced nuclear power systems for deployment in the late 1990's and in the next century.An overview of these developments and the key characteristics of these evolving advanced nuclear power plants are given in the paper.     

反应堆功率保成本控制器设计

针对反应堆功率控制系统设计中存在的建模误差以及实际运行过程中参数的不确定性,提出了一种新的功率保成本鲁棒控制器设计方法:运用线性矩阵不等式先求解出最优状态反馈保成本控制器,构造卡尔曼滤波器解决实际问题中状态不可测的问题,采用回路恢复的方法使总系统逼近目标反馈环传递函数.系统仿真结果表明,所设计的控制器实现了对设定功率的精确跟踪,解决了在堆模型不确定性、运行过程中参数不确定性下控制系统可能出现的不稳定和控制精度不够的问题,系统不但具有良好的鲁棒性,而且调节性能较好,满足堆功率调节控制的要求.     

The dynomak: An advanced spheromak reactor concept with imposed-dynamo current drive and next-generation nuclear power technologies

A high-β spheromak reactor concept has been formulated with an estimated overnight capital cost that is competitive with conventional power sources. This reactor concept utilizes recently discovered imposed-dynamo current drive (IDCD) and a molten salt (FLiBe) blanket system for first wall cooling, neutron moderation and tritium breeding. Currently available materials and ITER-developed cryogenic pumping systems were implemented in this concept from the basis of technological feasibility. A tritium breeding ratio (TBR) of greater than 1.1 has been calculated using a Monte Carlo N-Particle (MCNP5) neutron transport simulation. High temperature superconducting tapes (YBCO) were used for the equilibrium coil set, substantially reducing the recirculating power fraction when compared to previous spheromak reactor studies. Using zirconium hydride for neutron shielding, a limiting equilibrium coil lifetime of at least thirty full-power years has been achieved. The primary FLiBe loop was coupled to a supercritical carbon dioxide Brayton cycle due to attractive economics and high thermal efficiencies. With these advancements, an electrical output of 1000 MW from a thermal output of 2486 MW was achieved, yielding an overall plant efficiency of approximately 40%.     

DynMo-TE: Dynamic simulation model of space reactor power system with thermoelectric converters

A space reactor power system (SRPS) has been developed for avoidance of single point failures in reactor cooling and energy conversion. The sectored compact reactor (SCoRe) in this system is lithium-cooled and the reactor core is divided into six equal sectors with liquid metal heat pipes dividers. These reactor sectors are neutronically, but not thermal-hydraulically, coupled. Each sector has its own primary and secondary circulating lithium loops, which are thermally coupled both in a SiGe thermoelectric (TE) power conversion assembly (PCA) and a thermoelectric conversion assembly (TAC) that powers the electromagnetic pumps in the primary and secondary loops. Each secondary loop also has a separate, segmented radiator panel that is optimized for low specific mass and low liquid lithium inventory. The primary loops transport the thermal power generated in the reactor to six PCAs that nominally supply a total of 111.5 kW_e to the load at 450 V DC. Each of the 12 primary and secondary loops has its own bellows-type accumulator that is designed to regulate the lithium pressures in the loops. A dynamic simulation model of this thermoelectric SRPS (DynMo-TE) has been developed and used to investigate the transient operation of the system during a startup from a fully-thawed condition at 600 K, to nominal steady-state operation at which the lithium coolant exits the reactor at only 1179 K. Also investigated is the load-following characteristic of the SCoRe-TE SRPS, following a change in the electrical load demand.     

Automated recordkeeping of nuclear materials at electric power plants powered with a water-moderated-water-cooled nuclear reactor

Conclusions The automated nuclear-material recordkeeping system based on the NUMIS-2 program is at present being introduced at the Novororonezh electric power plant. Concurrently, the program is being modified in order to allow its use by the computer model being created in the COMECON member-nations. In the long term, it is expected that the recordkeeping program will become a component part of a single automated control systems of individual electric power plants.The NUMIS-2 program was approved for nuclear-material recordkeeping use after it was tested on the first fuel load of the fourth unit of the Novovoronezh electric power plant. The experiment confirmed the feasibility of automating the processing and storing of nuclear-material information and of recording that information and on the standard computer carriers of information. In principle, these same records can be submitted to the national recordkeeping service (or to the International Atomic Energy Agency) for their further immediate processing by means of the computer program employed by the service. In this manner, the recordkeeping system becomes closed, which makes it promising.We note that the propesed nuclear-material recordkeeping system satisfied the basic requirements of recordkeeping by computer laid down by the International Atomic Energy Agency as well as the required order of reporting by the plants under the control of the Agency.Translated from Atomnaya Énergiya, Vol. 45, No. 4, pp. 267–270, October, 1978.     

Self-contained co-generation nuclear power plant with integral nuclear reactor designed for remote and difficult-to-access areas

The paper gives an overview of the conceptual design of a reactor with enhanced safety intended for small NPPs to provide power supply for difficult-to-access and remote areas. The basic design features and the configuration of an integral nuclear reactor and the plant as a whole, as well as the main technical data are presented.     

Micro-structured nuclear fuel and novel nuclear reactor concepts for advanced power production

Many applications (e.g. terrestrial and space electric power production, naval, underwater and railroad propulsion and auxiliary power for isolated regions) require a compact-high-power electricity source. The development of such a reactor structure necessitates a deeper understanding of fission energy transport and materials behavior in radiation dominated structures. One solution to reduce the greenhouse-gas emissions and delay the catastrophic events' occurrences may be the development of massive nuclear power. The actual basic conceptions in nuclear reactors are at the base of the bottleneck in enhancements. The current nuclear reactors look like high security prisons applied to fission products. The micro-bead heterogeneous fuel mesh gives the fission products the possibility to acquire stable conditions outside the hot zones without spilling, in exchange for advantages – possibility of enhancing the nuclear technology for power production. There is a possibility to accommodate the materials and structures with the phenomenon of interest, the high temperature fission products free fuel with near perfect burning. This feature is important to the future of nuclear power development in order to avoid the nuclear fuel peak, and high price increase due to the immobilization of the fuel in the waste fuel nuclear reactor pools.     

Analysis of non-stationary fluctuations in a nuclear power reactor with temperature feedback

We analyse the behaviour of the neutron density and temperature fluctuations of a non-linear power reactor model during the transient regime. The equations for both fluctuations are derived by applying the system-size expansion method to the master equation which models the system. The behaviour of the fluctuations, assuming a temperature feedback effect, is analysed.