scholarly journals LITERATURE PERTINENT TO A STEAM GENERATOR DESIGN FOR A GAS-COOLED REACTOR SYSTEM

1958 ◽  
Author(s):  
R.I. Gray
Keyword(s):  
Steam Generator ◽  
Reactor System ◽  
Generator Design

Natural Circulation and Creep Damage Analyses of Severe Accident for a Typical PWR Plant

2009 ◽  
Author(s):  
Osamu Kawabata ◽  
Masao Ogino
Keyword(s):  
Steam Generator ◽  
Natural Circulation ◽  
Reactor Core ◽  
Creep Damage ◽  
Reactor Vessel ◽  
Reactor System ◽  
Severe Accident ◽  
Steam Generator Tube ◽  
Hot Gas ◽  
Core Meltdown

When the primary reactor system remain pressurized during core meltdown for a typical PWR plant, loop seals formed in the primary reactor system would lead to natural circulations in hot leg and steam generator. In this case, the hot gas released from the reactor core moves to a steam generator, and a steam generator tube would be failed with cumulative creep damage. From such phenomena, a high-pressure scenario during core meltdown may lead to large release of fission products to the environment. In the present study, natural circulation and creep damage in the primary reactor system accompanying the hot gas generation in the reactor core were discussed and the combining analysis with MELCOR and FLUENT codes were performed to examine the natural circulation behavior. For a typical 4 loop PWR plant, MELCOR code which can analyze for the severe accident progression was applied to the accident analyses from accident initiation to reactor vessel failure for the accident sequence of the main steam pipe break which is maintained at high pressure during core meltdown. In addition, using the CFD code FLUENT, fluid dynamics in the reactor vessel plenum, hot leg and steam generator of one loop were simulated with three-dimensional coordinates. And the hot gas natural circulation flow and the heat transfer to adjoining structures were analyzed using results provided by the MELCOR code as boundary conditions. The both ratios of the natural circulation flow calculated in the hot leg and the steam generator using MELCOR code and FLUENT code were obtained to be about 2 (two). And using analytical results of thermal hydraulic analysis with both codes, creep damage analysis at hottest temperature points of steam generator tube and hot leg were carried out. The results in both cases showed that a steam generator tube would be failed with creep rupture earlier than that of hot leg rupture.

Heat Recovery Steam Generator Design for a Graz Cycle Prototype Power Plant for CO2 Capture

2004 ◽  
Author(s):  
I. Giglmayr ◽  
J. Paul ◽  
W. Sanz
Keyword(s):  
Steam Generator ◽  
Gas Turbines ◽  
Heat Recovery ◽  
Fossil Fuels ◽  
Cost Effective ◽  
Pure Oxygen ◽  
Exhaust Gas ◽  
Heat Recovery Steam Generator ◽  
University Of Technology ◽  
Generator Design

The introduction of closed cycle gas turbines with their capability of retaining combustion generated CO2 can offer a valuable contribution to the Kyoto goal and to future power generation. Therefore, research and development at Graz University of Technology has lead to the GRAZ CYCLE, a zero emission power cycle of highest efficiency. The GRAZ CYCLE is still on a theoretical level, first tests with the turbo-machinery equipment were performed. In the GRAZ CYCLE fossil fuels are burned with pure oxygen which enables a cost-effective separation of the combustion generated CO2 by condensation. Cycle efficiencies as high as 63% can be reached. Taking the efforts for the oxygen supply into account the efficiency is reduced to 55% [1]. This work presents a further step towards a GRAZ CYCLE prototype plant, with special emphasis on the layout and design of the heat recovery steam generator (HRSG). The hot exhaust gas of the turbine consists mainly of CO2 and H2O. This exhaust gas causes higher demands on the HRSG. A faster corrosion of the heat exchangers and the recirculation of the cycle fluid have to be considered. Based on the design of conventional HRSGs, the necessary adaptations are discussed and economically evaluated.

Sensitivity Analysis for Dynamical Response of Reactor Coolant System Based on OPTIMUS

2020 ◽  
Author(s):  
Yuan Yanli ◽  
Ye Xianhui ◽  
Li Lijuan ◽  
Yuan Feng
Keyword(s):  
Sensitivity Analysis ◽  
Steam Generator ◽  
Nuclear Power ◽  
Reactor System ◽  
Response Analysis ◽  
Dynamical Response ◽  
Calculation Error ◽  
Reactor Coolant ◽  
Input Parameters ◽  
Coolant System

Abstract The sensitivity analysis of the dynamical response of reactor coolant system to the input parameters is an important precondition for the design optimization. In this paper, the sensitivity of the dynamical loads at the nozzles of the equipment under seismic conditions is analyzed with an integrated platform called OPTIMUS, taking the stiffness of the dampers in the steam generator and the main pump as the input variables. The key parameters of the reactor system are usually different from the design value due to the calculation error, random and other uncontrollable errors in the manufacturing process and installation process. In a nuclear power project, the measured stiffness values of the dampers on the steam generator and the main pump in the manufacturer are deviated from the requirements in the equipment specification, and it is necessary to evaluate the influence of the deviation on the dynamical response analysis of the reactor system. According to the traditional method, it is necessary to establish the models of the reactor coolant system for nonlinear analysis according to the different stiffness of the dampers, and then the calculation results are compared by EXCEL. In this paper, the sensitivity analysis of output parameters which are the loads at the nozzles of the equipment to the input parameters which are the stiffness of the dampers on the steam generator and pump is realized by OPTIMUS, which is a kind of integration platform. Not only can ANSYS simulation calculations be carried out automatically on the OPTIMUS, but also the output data can be processed rapidly automatically, and the influence of manufacturing deviation of the stiffness of the dampers on the dynamical response of the reactor coolant system can be analyzed quantitatively in the above-mentioned problems, and the data support is provided for the determination of the design variables for subsequent optimization analysis.

scholarly journals Russian and foreign steam generators for NPP power units with wet steam turbines

2020 ◽  
Vol 178 ◽  
pp. 01007
Author(s):  
Mikle Egorov ◽  
Ivan Kasatkin ◽  
Ivan Kovalenko ◽  
Irina Krectunova ◽  
Nataliya Lavrovskaya ◽  
...  
Keyword(s):  
Steam Generator ◽  
Nuclear Power ◽  
Temperature Drop ◽  
Heating Surface ◽  
Vessel Diameter ◽  
Absorption Efficiency ◽  
Steam Turbines ◽  
Steam Generators ◽  
Horizontal Type ◽  
Generator Design

The main aim of the current study is to analyze advantages and shortcomings of horizontal and vertical types of steam generator design. Design solutions and experience of operation of steam generators of horizontal type accepted in Russia and of vertical type applied by Westinghouse, Combustion Engineering, Siemens, Mitsubishi, Doosan were analyzed within the framework of the present study. It was established that steam generator equipment of horizontal type is characterized by disadvantages of design, technological and operational nature. Thus, horizontal steam generators with dimensions permissible for railroad transportation and, for VVER-1200 with reactor vessel diameter equal to 5 m, by water transport as well, have exhausted the possibilities for further significant increase of the per unit electric power. The demonstrated advantages of vertical-type steam generators are as follows: 1) absence of stagnant zones within the second cooling circuit; 2) uniformity of heat absorption efficiency of the heating surface that ensures improved conditions for moisture separation; 3) increased temperature drop with parameters of generated steam elevated by 0.3 – 0.4 MPa. Conclusion was made on the advisability of introduction of steam generators with vertical-type layout in the Russian nuclear power generation.

scholarly journals Development of a model for the wet steam separation in the steam space of PGV-1000M steam generator

Vestnik IGEU ◽  
2020 ◽  
pp. 5-15
Author(s):  
V.A. Gorbunov ◽  
N.A. Lonshakov ◽  
M.N. Mechtaeva
Keyword(s):  
Numerical Model ◽  
Steam Generator ◽  
Power Plants ◽  
Theoretical Calculations ◽  
Separation Process ◽  
Wet Steam ◽  
Three Dimensional Model ◽  
Element Analysis ◽  
Generator Design ◽  
Steam Separation

The issue of reducing steam humidity at the output of steam generator is relevant. The value of humidity directly affects the safety and efficiency of power plants. The optimization of steam generator design will enable to enhance its separation properties and reduce steam humidity. Creating a numerical model of wet steam separation process in a full-scale steam generator and its verification will allow proceeding to optimize the steam generator design and evaluate the model effectiveness. This article presents a preliminary study of the wet steam separation process in the steam space of PGV-1000M steam generator. To study the wet steam separation process in the steam space of PGV-1000M steam generator, a numerical model was developed in the ANSYS Fluent finite element analysis system. The following assumptions were made: the surface of the evaporation mirror is flat, drops have a spherical shape, they do not affect the movement of steam, they do not interact with each other, and there is no decay of the droplets. A three-dimensional model of the steam space of PGV-1000M steam generator which allows considering the processes of wet steam separation has been obtained. The analysis of the results has shown that the nature of the processes occurring in the model corresponds to theoretical calculations and operational data. The developed model has been verified and can be used to optimize the steam generator design. Further numerical studies of the developed model will enable to determine the most optimal design of the steam generator which provides the highest efficiency of steam separation. Moreover, it is possible and promising to study the effect of the evaporation mirror surface on the steam humidity in the steam generator. Decreasing the steam humidity at the steam generator output at existing and projected power plants will provide significant savings in funds spent on repairing the steam turbine blade apparatus, and will lead to an increase in the thermal efficiency of the plant.

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