Evaluation method of human-system interface for nuclear power plants

Author(s):  
Junichi TANJI ◽  
Jun KAWAI ◽  
Takao MASUI ◽  
Ikuko EZAKI
2019 ◽  
Vol 186 (4) ◽  
pp. 524-529
Author(s):  
Si Young Kim

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.


2011 ◽  
Vol 130-134 ◽  
pp. 3708-3711
Author(s):  
Chuan Sheng Xie ◽  
Sheng Ping Hua ◽  
Da Peng Dong ◽  
Xiao Xi Jia

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.


2021 ◽  
Vol 35 (3) ◽  
pp. 59-67
Author(s):  
Jung-Hyun Ryu

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.


2019 ◽  
Vol 205 (12) ◽  
pp. 1652-1660 ◽  
Author(s):  
Yuichi Morimoto ◽  
Masanori Akaike ◽  
Satoshi Takeo ◽  
Hiromi Maruyama

2009 ◽  
Vol 47 (7) ◽  
pp. 1016-1025 ◽  
Author(s):  
Yung-Tsan Jou ◽  
Chiuhsiang Joe Lin ◽  
Tzu-Chung Yenn ◽  
Chih-Wei Yang ◽  
Li-Chen Yang ◽  
...  

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