Seismic Fragility Study for High-Pressure Emergency Cooling Water Tanks of Loviisa Nuclear Power Plant

Author(s):  
Jukka Ka¨hko¨nen ◽  
Pentti Varpasuo

The paper studies the fragility of high-pressure emergency cooling water tanks in Loviisa Nuclear Power Plant located on the elevation +25.40 in the reactor building. The seismic fragility is defined as the conditional probability of its failure given a value of the response parameter, such as peak ground acceleration. Using the lognormal-distribution assumption, the fragility (i.e., the probability of failure, f′) at any non-exceedance probability level Q can be derived as Equation1f′=Φ[(ln(a/A¯)+βUΦ−1(Q))/βR] where Q = P(f<f′|a) is the probability that the conditional probability f is less than f′ for a peak ground acceleration a. A is the median ground acceleration capacity, βR is the logarithmic standard deviation representing the randomness about A, and βU is the logarithmic standard deviation representing the uncertainty. The quantity Φ(.) is the standard Gaussian cumulative distribution function. In order to assess the fragility of the tanks the strain time histories for tank supports and piping nozzles were calculated using the joint structural-equipment model. The ground motion response spectra shape used in the structural response analysis has been taken from the YVL 2.6 – guide [1]. This shape represents the envelope spectrum for Southern Finland corresponding to the median annual frequency of 10−5. The sampling of the model properties was carried out with the aid of the Latin hypercube sampling method. In order to find the failure modes the strain time histories were calculated for the piping nozzles and for support structures of the tanks. Since strain is the best measure of energy absorption, energy limited events need to be based on the strain acceptance criteria. The adopted failure limit is the cumulated plastic strain of 8% in the tank sheet metal or in the supporting structures. This failure limit has taken from the reference [2]. The end result of the study is the presentation of the median fragility curve for the tanks as well as 95% and 5% fractile curves.

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.


2015 ◽  
Vol 769 ◽  
pp. 235-240 ◽  
Author(s):  
Juraj Kralik

This paper presents the probabilistic safety assessment of nuclear power plant (NPP) in Slovakia due to earthquake event. The experiences from the deterministic and probabilistic seismic analyses of the structure resistance are mentioned. On the base of the geophysical and seismological monitoring of locality the peak ground acceleration was defined for the return period 104 years using the Monte Carlo simulations. The synthetic spectrum compatible accelerograms generated in program COMPACEL are presented in comparison with requirements of ASCE4/98 standard.


2019 ◽  
Vol 34 (3) ◽  
pp. 238-242
Author(s):  
Rex Abrefah ◽  
Prince Atsu ◽  
Robert Sogbadji

In pursuance of sufficient, stable and clean energy to solve the ever-looming power crisis in Ghana, the Nuclear Power Institute of the Ghana Atomic Energy Commission has on the agenda to advise the government on the nuclear power to include in the country's energy mix. After consideration of several proposed nuclear reactor technologies, the Nuclear Power Institute considered a high pressure reactor or vodo-vodyanoi energetichesky reactor as the nuclear power technologies for Ghana's first nuclear power plant. As part of technology assessments, neutronic safety parameters of both reactors are investigated. The MCNP neutronic code was employed as a computational tool to analyze the reactivity temperature coefficients, moderator void coefficient, criticality and neutron behavior at various operating conditions. The high pressure reactor which is still under construction and theoretical safety analysis, showed good inherent safety features which are comparable to the already existing European pressurized reactor technology.


2020 ◽  
Vol 1549 ◽  
pp. 052003
Author(s):  
Qiaojun Wu ◽  
Guangchu He ◽  
Hongyong Wen ◽  
Xinpeng Lin ◽  
Shengliang He ◽  
...  

Author(s):  
Qiaojun Wu ◽  
Guangchu He ◽  
Hongyong Wen ◽  
Xinpeng Lin ◽  
Shengliang He ◽  
...  

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