Multi-objective-based seismic fragility relocation for a Korean nuclear power plant

2020 ◽  
Vol 103 (3) ◽  
pp. 3633-3659 ◽  
Author(s):  
Shinyoung Kwag ◽  
Daegi Hahm
2020 ◽  
Vol 39 (5) ◽  
pp. 6339-6350
Author(s):  
Esra Çakır ◽  
Ziya Ulukan

Due to the increase in energy demand, many countries suffer from energy poverty because of insufficient and expensive energy supply. Plans to use alternative power like nuclear power for electricity generation are being revived among developing countries. Decisions for installation of power plants need to be based on careful assessment of future energy supply and demand, economic and financial implications and requirements for technology transfer. Since the problem involves many vague parameters, a fuzzy model should be an appropriate approach for dealing with this problem. This study develops a Fuzzy Multi-Objective Linear Programming (FMOLP) model for solving the nuclear power plant installation problem in fuzzy environment. FMOLP approach is recommended for cases where the objective functions are imprecise and can only be stated within a certain threshold level. The proposed model attempts to minimize total duration time, total cost and maximize the total crash time of the installation project. By using FMOLP, the weighted additive technique can also be applied in order to transform the model into Fuzzy Multiple Weighted-Objective Linear Programming (FMWOLP) to control the objective values such that all decision makers target on each criterion can be met. The optimum solution with the achievement level for both of the models (FMOLP and FMWOLP) are compared with each other. FMWOLP results in better performance as the overall degree of satisfaction depends on the weight given to the objective functions. A numerical example demonstrates the feasibility of applying the proposed models to nuclear power plant installation problem.


Author(s):  
G. SRINIVAS ◽  
A. K. VERMA ◽  
A. SRIVIDYA ◽  
SANJAY KUMAR KHATTRI

Technical Specifications define the limiting conditions of operation, maintenance and surveillance test requirements for the various Nuclear Power plant systems in order to meet the safety requirements to fulfill regulatory criteria. These specifications impact even the economics of the plant. The regulatory approach addresses only the safety criteria, while the plant operators would like to balance the cost criteria too. The attempt to optimize both the conflicting requirements presents a case to use Multi-objective optimization. Evolutionary algorithms (EAs) mimic natural evolutionary principles to constitute search and optimization procedures. Genetic algorithms are a particular class of EA's that use techniques inspired by evolutionary biology such as inheritance, mutation, natural selection and recombination (or cross-over). In this paper we have used the plant insights obtained through a detailed Probabilistic Safety Assessment with the Genetic Algorithm approach for Multi-objective optimization of Surveillance test intervals. The optimization of Technical Specifications of three front line systems is performed using the Genetic Algorithm Approach. The selection of these systems is based on their importance to the mitigation of possible accident sequences which are significant to potential core damage of the nuclear power plant.


Author(s):  
Chen Lei ◽  
Jia Zhen ◽  
Wang Cong ◽  
Gong Zili ◽  
Liao Yi ◽  
...  

From the view of practical engineering application, a compacter nuclear power plant is expected. The weight and the volume of a nuclear power plant can be reduced by optimal selection of the operational parameters. In this work, a thermal-hydraulic model of the reactor, mathematical models of the reactor vessel, the main pipe, the pressurizer, the steam generator, the turbine and the condenser were established for the Qinshan-I nuclear power plant based on the related technical materials. The responses of the optimal targets to the changes of the design variables were studied by the sensitivity analyses. The non-dominated solution front of the nuclear power plant was obtained by means of the immune memory clone constrained multi-objective optimization algorithm. The study shows that the component mathematical models are reliable for the optimization process, the distribution of the non-dominated solution is decided by the steam generator secondary pressure. The volume and the weight of the system could be at least reduced by 23.0% and 9.5%, respectively.


2020 ◽  
Vol 219 ◽  
pp. 110890
Author(s):  
Chunfeng Zhao ◽  
Na Yu ◽  
Yagiz Oz ◽  
Jingfeng Wang ◽  
Y.L. Mo

Author(s):  
Jianfeng Yang ◽  
Handing Wang ◽  
Xiaoming Zhang ◽  
Bingchen Feng ◽  
Weijin Wang ◽  
...  

According to the research of the operating principle, installation position and running environment of the 380VAC emergency electrical power distribution cabinets (Hereinafter referred to as electrical cabinets) of a nuclear power plant in China, there are three aspects caused by earthquake that seriously affect the safety of the electrical cabinets, including relay chatter, failure of electrical cabinet structure and spatial interactions. Relay chatter refers to contacts of the relay being changed during the period of strong shaking. It may lead to associated circuits malfunction and the equipment failure of the relay control unless it can be effectively reset. The purpose of relay chatter is to find out these relays whose consequences are unacceptable after earthquake and calculate failure probability. Failure of electrical cabinet structure in the earthquake is to carry out seismic fragility evaluation. The goal of seismic fragility evaluation is to assess a given value which describes the ground acceleration capacity and the corresponding uncertainties, and then, the conditional probability of failure as a function of peak ground acceleration [PGA] and a family of fragility curves can be obtained. In this paper, finite element model of the electrical cabinet is established using ANSYS Workbench software. According to the electric cabinets seismic failure mode, we take some of the parameters including the parameters of the floor response spectrum, material strength parameters and so on as the input to calculate the median ground acceleration capacity and the corresponding uncertain parameters. The seismic spatial interactions are defined as the electrical cabinet destroyed due to the surrounding objects failure by falling, collapse, etc. Therefore, if necessary, it is needed to evaluate the seismic fragility of the surrounding objects. Usually through walking down, checking the design drawings or the combination of the above methods, we can find out the surrounding objects for an electric cabinet. So we analyze the seismic risk of the electrical cabinet from the above three aspects. When the results of the above three aspects obtained, we convolute of the electrical cabinet fragility with the seismic hazard curve which represents the frequency of occurrence of earthquake motions at various levels of intensity at the site. Then Monte Carlo sampling is adopted to analyze the uncertainty distribution. In this article, Risk Spectrum Professional software (reference 8) and Risk Spectrum Hazard lite software (reference 9) are used to complete the calculation and get some quantitative seismic risk insights. The above seismic risk insights can support the establishment of seismic probabilistic safety analysis model (Hereinafter referred to as SPSA) for a nuclear power plant, which helps to formulate seismic improvement strategies.


Sign in / Sign up

Export Citation Format

Share Document