scholarly journals Uniform Hazard Spectrum Evaluation Method for Nuclear Power Plants on Soil Sites based on the Hazard Spectra of Bedrock Sites

2012 ◽  
Vol 16 (3) ◽  
pp. 35-42 ◽  
Author(s):  
Dae-Gi Hahm ◽  
Jeong-Moon Seo ◽  
In-Kil Choi ◽  
Hyun-Me Rhee
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Uniform Hazard Spectrum ◽  
Spectrum Evaluation

INTERCOMPARISON ON INTERNAL DOSE ASSESSMENT FOR NUCLEAR POWER PLANTS IN KOREA

2019 ◽  
Vol 186 (4) ◽  
pp. 524-529
Author(s):  
Si Young Kim
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Dose Assessment ◽  
Assessment Procedure ◽  
Internal Dose ◽  
Nuclear Facilities ◽  
International Intercomparison ◽  
Selection Of

Abstract The intercomparison test is a quality assurance activity performed for internal dose assessment. In Korea, the intercomparison test on internal dose assessment was carried out for nuclear facilities in May 2018. The test involved four nuclear facilities in Korea, and seven exposure scenarios were applied. These scenarios cover the intake of 131I, a uranium mixture, 60Co and tritium under various conditions. This paper only reviews the participant results of three scenarios pertinent to the operation of nuclear power plants and adopts the statistical evaluation method, used in international intercomparison tests, to determine the significance values of the results. Although no outliers were established in the test, improvements in the internal dose assessment procedure were derived. These included the selection of intake time, selection of lung absorption type according to the chemical form and consideration of the contribution of previous intake.

Security Risk Analysis of Nuclear Power Plants Based on Fuzzy Comprehensive Evaluation

2011 ◽  
Vol 130-134 ◽  
pp. 3708-3711
Author(s):  
Chuan Sheng Xie ◽  
Sheng Ping Hua ◽  
Da Peng Dong ◽  
Xiao Xi Jia
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Comprehensive Evaluation ◽  
Risk Index ◽  
Fuzzy Comprehensive Evaluation ◽  
Security Risk ◽  
Fuzzy Comprehensive Evaluation Method ◽  
Comprehensive Evaluation Method

A fuzzy comprehensive evaluation method for nuclear power plants is introduced in this article. First, a risk index system is established of which these indicators will be explained accordingly latter. Then, an evaluation set is constructed, and the weight of each index and corresponding membership is determined according to suggestions of experts and membership function to make evaluation level by level ，until a final comprehensive evaluation is obtained. This method is not very objective but simple and available.

scholarly journals Fire Risk Assessment of Transient Ignition Sources in Domestic Nuclear Power Plants

2021 ◽  
Vol 35 (3) ◽  
pp. 59-67
Author(s):  
Jung-Hyun Ryu
Keyword(s):  
Risk Assessment ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Fire Risk ◽  
Ignition Source ◽  
Fire Risk Assessment

The fire risk of a nuclear power plant is evaluated using fixed and transient ignition sources. In terms of the overall fire risk, the proportion of transient ignition sources is very small. However, because the uncertainty due to the difference between the assumptions and the modeling method is relatively large, it is necessary to establish a methodology to address this. In this study, the new transient ignition source evaluation method presented in NUREG/CR-6850, the ignition source frequency revised in NUREG-2169, and the input parameters for transient fire modeling presented in NUREG-2233 were used to evaluate the fire risk assessment for transient ignition sources. In this new evaluation methodology, the fire ignition frequency is quantitatively evaluated based on the characteristics of the area, and an area-based scenario evaluation method considering the location of the transient ignition source is proposed for the evaluation within the area. As a result of applying the new methodology to the switchgear room of a reference nuclear power plant, an approximately 70% risk reduction was confirmed compared to the existing EPRI TR-105928 method. In the future, if fire risk assessment for transient ignition sources in nuclear power plants is applied using the results of this study, it is expected that areas whose control is important in the event of a fire can be determined, which should help reduce highly rated fire risks.

Proposal of a Statistical Evaluation Method for the Criticality of the Fukushima Daiichi Nuclear Power Plants

2019 ◽  
Vol 205 (12) ◽  
pp. 1652-1660 ◽  
Author(s):  
Yuichi Morimoto ◽  
Masanori Akaike ◽  
Satoshi Takeo ◽  
Hiromi Maruyama
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Statistical Evaluation ◽  
Fukushima Daiichi

Updated Knowledge Implemented to the Revision of Environmental Fatigue Evaluation Method for Nuclear Power Plant in JSME Code

2009 ◽  
Author(s):  
Makoto Higuchi ◽  
Takao Nakamura ◽  
Yasuaki Sugie
Keyword(s):  
Power Generation ◽  
Fatigue Life ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Power Engineering ◽  
Nuclear Power Generation ◽  
Fatigue Data ◽  
Fatigue Evaluation

Many examinations concerning the fatigue life reduction for structural materials of nuclear power plants in water simulated LWR coolants had been carried out after the first paper had been recognized in Japan [1, 2]. Based on these results, the method to evaluate the fatigue damage for the materials exposed to the LWR coolant had been developed. After 1990s in Japan, the Environmental Fatigue Data Committee (EFD) of the Thermal and Nuclear Power Engineering Society (TENPES), the Project on Environmental Fatigue Testing (EFT) supported by the Japan Power Engineering and Inspection Corporation (JAPEIC) and the Japan Nuclear Energy Safety Organization (JNES) and some utility joint studies have investigated the environmental fatigue. In September 2000, the Nuclear Power Generation Safety Management Division of the Agency for Natural Resources and Energy, Ministry of International Trade and Industry issued “Guidelines for Evaluating Fatigue Initiation Life Reduction in the LWR Environment” (hereafter, called “the MITI Guidelines”) [3]. These guidelines include an equation to evaluate environmental fatigue and require electric utilities to consider the environmental effects in their Plant Life Management (PLM) activities. However, the MITI Guidelines do not provide specific and practical techniques for evaluating environmental fatigue under actual plant conditions. Accordingly, TENPES took on the task to produce one. In 2002 TENPES issued the “Guidelines on Environmental Fatigue Evaluation for LWR Component” [4, 5] (hereafter, called “the TENPES Guidelines”) based on the techniques developed by the EFD Committee. A set of Rules, called the Environmental Fatigue Evaluation Method (EFEM), was established in the Codes for Nuclear Power Generation Facilities - Environmental Fatigue Evaluation Method for Nuclear Power Plants (JSME S NF1-2006, EFEM-2006)[6], which was issued in March 2006 by reviewing the equations for the environmental fatigue life correction factor, Fen, specified in the MITI Guidelines, and the techniques for evaluating environmental fatigue specified in the TENPES Guidelines, and considering the new environmental fatigue data including JNES-SS report (August 2005) [7]. The EFEM revised version has been drafted by incorporating the updated knowledge described in JNES-SS report (April 2007) [8] and is scheduled to be issued by the end of 2009. This paper introduces the revision in it and their technical basis. Additionally, future issues are addressed to be considered in the improvement of the EFEM.

The Investigation of Classification Management for SSCS Susceptible to Ageing in PWR

2010 ◽  
Author(s):  
Fei Xue ◽  
Peng Liu ◽  
Xin-ming Meng ◽  
Wen-xin Ti ◽  
Lei Lin ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Residual Life ◽  
Classification Method ◽  
Energy Agency ◽  
Pressurized Water ◽  
Management Method ◽  
Classification Management

A set of screening and classification method is proposed in this paper to manage the Systems, Structures and Components (SSCs) of the Pressurized Water Reactor (PWR) for the aging management. The method proposed and carried out in China Nuclear Power Plants (NPP) is based on the systematic aging evaluation method and the management method for the license renewal from International Atomic Energy Agency (IAEA) and U.S. Nuclear Regulatory Commission (NRC), whose successful management methods are discussed in this paper. Considering the importance of the classification management of the SSCs, the classification method is investigated from the aspects of the safety, reliability and replacement of the SSCs with the Nuclear Power Plant operation experience feed-back. With the classification management method, the SSCs are managed economically and effectively for the Nuclear Power Plants in China. The method also makes great foundation for the aging management and residual life evaluation of the PWR in China.

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