Numerical study to reproduce a real cable tray fire event in a nuclear power plant
2
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
In this study, a numerical analysis was performed as part of an international joint research project to reproduce a real cable tray fire that occurred in the heater bay area of the turbine building of a nuclear power plant. A sensitivity analysis was performed on various input parameters to derive results consistent with the sprinkler activation time obtained from the fire event analysis. For all sensitive parameters, the normalized sprinkler activation time correlated well with the power function of the normalized sprinkler height. A correlation equation was developed to identify the sprinkler activation time at any location when determining the slope or fire growth rate under the conditions assuming a linear or t-squared heat release rate (HRR) time curve. Various cable fire growth assumptions were used to determine which assumption was better to provide the prediction coincident with the information given from the fire event analysis in terms of the sprinkler activation time and total energy generated from cables damaged by fire. In the comprehensive analysis of all the sensitive parameters, the standard deviation of the input parameters increased as the sprinkler height decreased. Within the range of the sensitivity parameter values given in this study, when considering all sprinkler heights, the standard deviation of the cable model change was the largest and that of the overhang position change was the smallest.
Abstract
In this study, a numerical analysis was performed as part of an international joint research project to reproduce a real cable tray fire that occurred in the heater bay area of the turbine building of a nuclear power plant. A sensitivity analysis was performed on various input parameters to derive results consistent with the sprinkler activation time obtained from the fire event analysis. For all sensitive parameters, the normalized sprinkler activation time correlated well with the power function of the normalized sprinkler height. A correlation equation was developed to identify the sprinkler activation time at any location when determining the slope or fire growth rate under the conditions assuming a linear or t-squared heat release rate (HRR) time curve. Various cable fire growth assumptions were used to determine which assumption was better to provide the prediction coincident with the information given from the fire event analysis in terms of the sprinkler activation time and total energy generated from cables damaged by fire. In the comprehensive analysis of all the sensitive parameters, the standard deviation of the input parameters increased as the sprinkler height decreased. Within the range of the sensitivity parameter values given in this study, when considering all sprinkler heights, the standard deviation of the cable model change was the largest and that of the overhang position change was the smallest.
참고문헌 (28)
- L. Audouin, "OECD PRISME project : fires in confined and ventilated nuclear-type multi-compartments-Overview and main experimental results", Fire Saf. J, 62, pp.80~101 (2017)
- Investigating Heat and Smoke Propagation Mechanisms in Multi-compartment Fire ScenariosdFinal Report of the PRISME Project, "L. Rigollet", NEA, 2017
- S. Bascou, "Benchmark activity of the OECD", NEA PRISME 3 and FIRE projects, 2019, ~[DOI]
- Committee on the Safety of Nuclear Installations (CSNI):PRISME Project Application Report, "Organisation for Economic Co-operation and Development", Committee on the Safety of Nuclear Installations (CSNI), ~, pp.PRISME Project Application Report, 14, NEA (2012), CSNI[DOI]
- Overview of the OECD PRISME 3 project, Fire Safety and Emergency Preparedness for the Nuclear Industry, "S. Suard", FSEP, ~, pp.Chal-02465442D (2019)
- Y. H. Jung, "Benchmark Simulations of Cable Tray Fires in PRISME CFS and CFP Tests", Transactions of the Korean Nuclear Society virtual spring meeting (2021)
- K. McGrattan, "Fire Dynamics Simulator User's Guide" (2013), National Institute of Standards and Technology (NIST)
- C. S. Lin, "Modeling and analysis of a bus fire accident for evaluation of fire safety door using the fire dynamics simulator", Cluster Comput, 22(6), pp.14973~14981 (2019)
- T. S. Shen, "Using fire dynamic simulation(FDS)to reconstruct an arson fire scene", Build. Environ, 43(6), pp.1036~1045 (2008)
- J. H. Chi, "Reconstruction of an inn fire scene using the Fire Dynamics Simulator(FDS)program", J. Forensic Sci, 58, pp.227~234 (2013)
- W. C. Park, "Simulation of smoke control in a subway station fire", Fire Saf. Sci, 6, pp.8b~ (2004)
- C. Caliendo, "Simulation of people evacuation in the event of a road tunnel fire", Procedia-social and behavioral sciences, 53, pp.178~188 (2012)
- Nils Johansson, "Variation in Results Due to User Effects in a Simulation with FDS", Fire Technology, 54(1), pp.97~116 (2017), Springer Science and Business Media LLC[DOI]
- Cable heat release ignition, and spread in tray installations during fire (CHRISTIFIRE) phase 1: horizontal trays, "K. McGrattan", National Institute of Standards and Technology (NIST), ~, pp.NUREG (2012), CR-7010, 1
- P. Zavaleta, "Improved assessment of fire spread over horizontal cable trays supported by video fire analysis", Fire Technol, 55(1), pp.233~255 (2019)
- A. Jenft, "Etude des interactions entre phenomenes d'incendie et systemes d'extinctiona eau. Developpement d'un module d'extinction dans le logiciel FDS", Doctor, pp.2013
- 이재호, "Numerical analysis on the rapid fire suppression using a water mist nozzle in a fire compartment with a door opening", Nuclear Engineering and Technology, 51(2), pp.410~423 (2019), 한국원자력학회[DOI]
- P. Zavaleta, "Cable tray fire tests with halogenated electric cables in a confined and mechanically-ventilated facility", Fire Mater, 43(5), pp.431~609 (2019)
- Nuclear Power Plant Fire Modeling Analysis Guidelines, "U. S. NRC", United States Nuclear Regulatory Commission, ~, pp.NUREG-1934 (2012)
- W. Plumecocq, "Numerical method for determining water droplets size distributions of spray nozzles using a two-zone model", Nucl. Eng. Des, 324, pp.67~77 (2017)
- Verification and validation of selected fire models for nuclear power plant applications, "U. S. Nrc", ~, pp.No. NUREG-1824, supplement 1 (2016)
- J. Lee, "Numerical analysis of how ventilation conditions impact compartment fire suppression by water mist", Ann. Nucl. Energy, 136, pp.107021~ (2020)
- J. Lee, "Numerical analysis of the effect of horizontal distance between a water mist nozzle and ignition source on reduction in heat release rate", Ann. Nucl. Energy, 144, pp.107560~ (2020)
- 이재호, "물 분무 액적 특성이 화재진압에 미치는 영향에 대한 수치해석", 한국화재소방학회 논문지, 33(6), pp.1~8 (2019), 한국화재소방학회[DOI]
- M. F. Abdrabbo, "The effect of water mist droplet size and nozzle flow rate on fire extinction in hanger by using FDS", J. Civ. Environ. Eng, 6 (2016)
- J. Hua, "A numerical study of the interaction of water spray with a fire plume", Fire Saf. J, 37(7), pp.631~657 (2002)
- Study of Damageability of Electrical Cables in Simulated Fire Environments, "J.L. Lee", Factory Mutual Research Corp, ~, pp.No. EPRI-NP-1767 (1981)
- 하각현, "Numerical analysis to determine fire suppression time for multiple water mist nozzles in a large fire test compartment", Nuclear Engineering and Technology, 53(4), pp.1157~1166 (2021), 한국원자력학회[DOI]
