Hydrogen Fire Risk Analysis on CPR1000 System of Fangchenggang Nuclear Power Plant

2021 ◽  
Vol 09 (01) ◽  
pp. 21-28
Author(s):  
学进 周
2016 ◽  
Vol 94 ◽  
pp. 409-414 ◽  
Author(s):  
Yu Yu ◽  
Nan Ma ◽  
Yuan Peng ◽  
Xuefeng Lv ◽  
Fenglei Niu ◽  
...  

Risk Analysis ◽  
1985 ◽  
Vol 5 (1) ◽  
pp. 33-51 ◽  
Author(s):  
Mardyros Kazarians ◽  
Nathan O. Siu ◽  
George Apostolakis

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.


2009 ◽  
Vol 2009 ◽  
pp. 1-10 ◽  
Author(s):  
Jinbiao Xiong ◽  
Yanhua Yang ◽  
Xu Cheng

A three dimensional computation fluid dynamics (CFD) code, GASFLOW, is applied to analyze the hydrogen risk for Qinshan-II nuclear power plant (NPP). In this paper, the effect of spray modes on hydrogen risk in the containment during a large break loss of coolant accident (LBLOCA) is analyzed by selecting three different spray strategies, that is, without spray, with direct spray and with both direct and recirculation spray. A strong effect of spray modes on hydrogen distribution is observed. However, the efficiency of the passive auto-catalytic recombiners (PAR) is not substantially affected by spray modes. The hydrogen risk is significantly increased by the direct spray, while the recirculation spray has minor effect on it. In order to simulate more precisely the processes involved in the PAR operation, a new PAR model is developed using CFD approach. The validation shows that the results obtained by the model agree well with the experimental results.


Author(s):  
Nathan O. Siu ◽  
Nicholas Melly ◽  
Steven P. Nowlen ◽  
Mardy Kazarians

2007 ◽  
Vol 4 (5) ◽  
pp. 100469
Author(s):  
Jill E. Norcott ◽  
Thomas K. Blanchat ◽  
M. Hirschler ◽  
S. W. Dean

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