Application of PSO in the Optimization of Nuclear Power Unit’s Heat Regenerative System

2014 ◽  
Vol 986-987 ◽  
pp. 698-701
Author(s):  
Wen Feng Fu ◽  
Fe Li ◽  
Lan Xin Zhou

Based on theoretical deduction, according to the characteristics of nuclear power unit, a universal heat economic framework for PWR nuclear power plant heat regenerative system was established. And on this basis, the cycle thermal efficiency was chosen as the optimization goal, the extraction steam pressures were chosen as optimization variables, a universal nuclear power unit regenerative system optimization model was established. A 900 MW nuclear power unit was taken for example, it’s the first time that AWPSO was applied to optimize the regenerative heat system of nuclear power unit. The result shows that the convergence ability and search performance of PSO are superior to other methods and the original design scheme. A new and convenient design is provided for PWR nuclear power plant heat regenerative system in this paper.

2021 ◽  
Vol 2 (396) ◽  
pp. 149-158
Author(s):  
I. Chesnokova ◽  
◽  
S. Verbitsky ◽  
E. Stambrovskaya ◽  
◽  
...  

Object and purpose of research. The article discusses in comparison the methods of desalination of seawater and their energy features from the point of view of the feasibility of including a desalination plant in the complex with a floating nuclear power unit. Materials and methods. Based on the analysis of various literary sources, a review of the main methods of nuclear desalination is made. The IAEA DEEP program was used to compare different desalination technologies. Main results. Based on the results of simulating nuclear desalination in the IAEA DEEP program, using the example of the Persian Gulf, preliminary recommendations were drawn up on the use of desalination methods in the joint operation of a desalination plant with a floating nuclear power unit. Conclusion. The integrated complex allows for desalination by both membrane and thermal methods. For the optimal choice of technology, it is necessary to specify the area of deployment and the relative position of the floating nuclear power unit and the desalination plant, and further search for a compromise based on more accurate calculations.


Author(s):  
R. Z. Aminov ◽  
A. N. Bairamov

THE PURPOSE. System efficiency and competitiveness assess of a new scheme for combining a nuclear power plant with a hydrogen complex based on additional heating of feed water and superheating of live steam in front of the high-pressure cylinder of a steam turbine. METHODS. Basic laws of thermodynamics were applied when developing and substantiating a new scheme for combining a nuclear power plants (NPP) with a hydrogen facility; theoretical regularities were applied of heat engineering; basic regularity were applied of fatigue wear of power equipment and assessment of its working resourse; basic regularities were applied for the assessment of operating costs and net present value (NPV). RESULTS. A new scheme is presented of the combination of a nuclear power plant with a hydrogen facility and a description of its operating principle on the example of a two-circuit nuclear power plant with a VVER-1000 reactor and a C-1000-60 / 1500 turbine. The data are presented on an increase in the productivity of steam generators at nuclear power plants with additional heating of feed water in the range of 235-250 ° C from its nominal value of 230 ° C. The temperature was estimated of live steam superheat depending on the temperature of the additional heating of the feed water. The results are presented of the calculation of the generated peak power by the power unit and the efficiency of conversion of the night off-peak power of the NPP into peak power, as well as the efficiency of the power unit of the NPP depending on the temperature of additional heating of the feed water. Main regularities are given for taking into account the fatigue wear of the main equipment of the hydrogen facility, including the rotor of the NPP turbine in the conditions of the stress-cyclic operation. The results are presented of assessing the cost of peak electricity NPP in combination with a hydrogen facility in comparison with a pumped storage power plant (PSPP) both for the current period and for the future until 2035. CONCLUSION. Hydrogen facility efficiency and competitiveness depends significantly on the intensity of the use of the main equipment in the conditions of the intense-cyclic operation. The hydrogen facility will competitiveness noticeably increase in comparison with the PSPP in the future. Efficiency of the NPP power unit and NPV is highest when the feed water is heated to 235 ° C and superheating of live steam in front of the high-pressure cylinder of the C-1000-60/1500 turbine up to 470°C.The hydrogen facility competes with the PSPP with her specific capital investment at the level of 660 USD / kW, provided that the boosting capabilities of the turbine are used with live steam overheating at 300 ° C and additional heating of feed water to 235°C on the current period. The PSPP does not compete with the hydrogen facility both for the current period and in the future with her specific capital investment of $ 1,500 / kW and above.


ANRI ◽  
2021 ◽  
Vol 0 (4) ◽  
pp. 60-76
Author(s):  
Lev Belovodskiy ◽  
Aleksandr Panfilov

This year marks the 35-th anniversary of the events related to the liquidation of the consequences of the accident at the Chernobyl nuclear power plant (Chernobyl NPP) and their most important stage - the closure of the destroyed 4-th power unit with a special structure, which was initially called the «Sarcophagus» (later the «Shelter» object). This article presents information about the period May-November 1986 in the aspect of radiation safety of the builders of this unique facility.


2016 ◽  
Vol 853 ◽  
pp. 346-350
Author(s):  
Lin Wei Ma ◽  
Jia Sheng He ◽  
An Qing Shu ◽  
Xiao Tao Zheng ◽  
Yan Wang

Primary water stress corrosion cracking (PWSCC) has been observed in CRDM nozzles, BMI nozzles and other penetration nozzles. The industry has used the repair method of replacement of nozzles fabricated of Alloy 690. After the replacement of the nozzle, the structural integrity analysis of new nozzle and welds should be performed to ensure the pressure boundary compliance with the original design requirement. In this paper, the pressurizer top head instrument nozzle of PWR nuclear power plant is evaluated as a typical pressure vessel penetration nozzle. The results showed that the repaired nozzle satisfies the ASME Code design requirement and the crack growth of the postulated flaw in 40 years of the nuclear plant life is acceptable.PWSCC degradation mechanism has been observed in CRDM nozzles, BMI nozzles and other penetration nozzles [1]. In some nuclear power plants built in China earlier, such as DAYABAY nuclear power plant and QINSHAN nuclear power plant, PWSCC degradation mechanism has been found in CRDM nozzle welds which manufactured of Alloy 600 and welded of Alloy 82/182[2]. The repair of the degraded nozzles is the popular choice for the nuclear power plant owners. After the replacement of the nozzle, the structural integrity analysis of new nozzle and welds should be performed to ensure the pressure boundary compliance with the original design requirement. In this paper, the pressurizer top head nozzle of PWR nuclear power plant is evaluated as a typical pressure vessel penetration nozzle. Stress intensities were conservatively determined for pressure and applicable thermal transients and compared to the allowable values of the ASME Code, Section III. Thermal stress of the transients was obtained from 3D finite element model (FEM). Residual stress of J-groove weld was obtained from 2D FEM analysis and used for fracture mechanics analysis. All of the analysis showed that the repaired nozzle satisfies the ASME Code design requirement and the crack growth of the postulated flaw in 40 years of the nuclear plant life is acceptable.


1982 ◽  
Vol 19 (3) ◽  
pp. 87-89
Author(s):  
V. I. Ryzhenkov ◽  
A. P. Dubyaga ◽  
V. N. Uvarkin ◽  
N. A. Ivanov

1981 ◽  
Vol 25 (1) ◽  
pp. 163-167 ◽  
Author(s):  
Mark Kirkpatrick ◽  
Kenneth Mallory

Nuclear power plant control rooms contain large numbers of identical or similar control and display components. The discrimination cues available for selecting a single component are frequently minimal. This situation can lead to substitution errors in which the wrong display is read or the wrong control is operated. An example of such an error is discussed in relation to a generic procedure sequence and remedial approaches are presented with respect to both original design and modification of existing control panels.


2014 ◽  
Vol 1008-1009 ◽  
pp. 231-236
Author(s):  
Zuo Liang Yang ◽  
Zhi Gang Dai ◽  
Tong Bin Wang

This paper presented a novel method for using Genetic Algorithm (GA) to solve the problem of Feed-water Enthalpy Rise Optimum Distribution in nuclear power unit. According to the characteristics of the pressurized-water reactor unit's secondary circuit, the calculation equations for the power and the heat rate of steam turbine are given in matrix form, the rate of extraction steam is calculated by the general matrix thermal balance equation, and then receive the equation of the efficiency of steam turbine which has relative with parameters of every node in the thermodynamic system in PWR unit. Taking the efficiency equation as aim function, an effective fitness-model was established with the appropriate optimum parameters under the restriction condition, the feed-water enthalpy rise distribution is optimized under the restriction condition by means of Genetic Algorithm. Through the calculation of a 600MW PWR nuclear power unit, the results indicate that Genetic Algorithm has global searching performance, gives a better global optimum than original design value rapidly and shows the relations between the optimum parameters (even the temp parameters) and the optimization easily. Genetic Algorithm is a promising method for analyzed and solved the feed-water enthalpy rise optimum distribution in PWR nuclear power unit.


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