PARZER, Iztok ;MAVKO, Borut . Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant. Strojniški vestnik - Journal of Mechanical Engineering, [S.l.], v. 49, n.9, p. 430-444, july 2017. ISSN 0039-2480. Available at: <https://www.sv-jme.eu/sl/article/simulation-of-a-hypothetical-loss-of-feedwater-accident-in-a-modernized-nuclear-power-plant/>. Date accessed: 20 dec. 2024. doi:http://dx.doi.org/.
Parzer, I., & Mavko, B. (2003). Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant. Strojniški vestnik - Journal of Mechanical Engineering, 49(9), 430-444. doi:http://dx.doi.org/
@article{.,
author = {Iztok Parzer and Borut Mavko},
title = {Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant},
journal = {Strojniški vestnik - Journal of Mechanical Engineering},
volume = {49},
number = {9},
year = {2003},
keywords = {nuclear power plants; loss of feedwater; accidents-simulations; software package; RELAP5/MOD2; },
abstract = {Simulators of this type are used for training and maintaining competence to ensure the safe and reliable operation of nuclear power plants throughout the world. In this study the response of the modernized Krko nuclear power plant (NPP) to a total-loss-of-feedwater accident, leading to the total loss of the secondary heat sink, was calculated. Based on these results, the validation of the full-scope simulator was performed. The verified plant-specific RELAP5/MOD2 input model of the Krko NPP, adapted for the 2000 MWt power (cycle 17), including the model for replacement steam generators, was used. Core heatup occurred in the analyzed case. Core degradation and melting are outside the scope of the RELAP5/MOD2 best-estimate code simulation, but it can predict all the events up to the moment when the core cladding temperature starts to approach the melting point. The comparison of the Krko full-scope simulator (KFSS) data with the calculated reference data shows good agreement and indicates that the simulator-validation testing for this kind of accident was successful.},
issn = {0039-2480}, pages = {430-444}, doi = {},
url = {https://www.sv-jme.eu/sl/article/simulation-of-a-hypothetical-loss-of-feedwater-accident-in-a-modernized-nuclear-power-plant/}
}
Parzer, I.,Mavko, B. 2003 July 49. Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant. Strojniški vestnik - Journal of Mechanical Engineering. [Online] 49:9
%A Parzer, Iztok %A Mavko, Borut %D 2003 %T Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant %B 2003 %9 nuclear power plants; loss of feedwater; accidents-simulations; software package; RELAP5/MOD2; %! Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant %K nuclear power plants; loss of feedwater; accidents-simulations; software package; RELAP5/MOD2; %X Simulators of this type are used for training and maintaining competence to ensure the safe and reliable operation of nuclear power plants throughout the world. In this study the response of the modernized Krko nuclear power plant (NPP) to a total-loss-of-feedwater accident, leading to the total loss of the secondary heat sink, was calculated. Based on these results, the validation of the full-scope simulator was performed. The verified plant-specific RELAP5/MOD2 input model of the Krko NPP, adapted for the 2000 MWt power (cycle 17), including the model for replacement steam generators, was used. Core heatup occurred in the analyzed case. Core degradation and melting are outside the scope of the RELAP5/MOD2 best-estimate code simulation, but it can predict all the events up to the moment when the core cladding temperature starts to approach the melting point. The comparison of the Krko full-scope simulator (KFSS) data with the calculated reference data shows good agreement and indicates that the simulator-validation testing for this kind of accident was successful. %U https://www.sv-jme.eu/sl/article/simulation-of-a-hypothetical-loss-of-feedwater-accident-in-a-modernized-nuclear-power-plant/ %0 Journal Article %R %& 430 %P 15 %J Strojniški vestnik - Journal of Mechanical Engineering %V 49 %N 9 %@ 0039-2480 %8 2017-07-07 %7 2017-07-07
Parzer, Iztok, & Borut Mavko. "Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant." Strojniški vestnik - Journal of Mechanical Engineering [Online], 49.9 (2003): 430-444. Web. 20 Dec. 2024
TY - JOUR AU - Parzer, Iztok AU - Mavko, Borut PY - 2003 TI - Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant JF - Strojniški vestnik - Journal of Mechanical Engineering DO - KW - nuclear power plants; loss of feedwater; accidents-simulations; software package; RELAP5/MOD2; N2 - Simulators of this type are used for training and maintaining competence to ensure the safe and reliable operation of nuclear power plants throughout the world. In this study the response of the modernized Krko nuclear power plant (NPP) to a total-loss-of-feedwater accident, leading to the total loss of the secondary heat sink, was calculated. Based on these results, the validation of the full-scope simulator was performed. The verified plant-specific RELAP5/MOD2 input model of the Krko NPP, adapted for the 2000 MWt power (cycle 17), including the model for replacement steam generators, was used. Core heatup occurred in the analyzed case. Core degradation and melting are outside the scope of the RELAP5/MOD2 best-estimate code simulation, but it can predict all the events up to the moment when the core cladding temperature starts to approach the melting point. The comparison of the Krko full-scope simulator (KFSS) data with the calculated reference data shows good agreement and indicates that the simulator-validation testing for this kind of accident was successful. UR - https://www.sv-jme.eu/sl/article/simulation-of-a-hypothetical-loss-of-feedwater-accident-in-a-modernized-nuclear-power-plant/
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author = {Parzer, I., Mavko, B.},
title = {Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant},
journal = {Strojniški vestnik - Journal of Mechanical Engineering},
volume = {49},
number = {9},
year = {2003},
doi = {},
url = {https://www.sv-jme.eu/sl/article/simulation-of-a-hypothetical-loss-of-feedwater-accident-in-a-modernized-nuclear-power-plant/}
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TY - JOUR AU - Parzer, Iztok AU - Mavko, Borut PY - 2017/07/07 TI - Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant JF - Strojniški vestnik - Journal of Mechanical Engineering; Vol 49, No 9 (2003): Strojniški vestnik - Journal of Mechanical Engineering DO - KW - nuclear power plants, loss of feedwater, accidents-simulations, software package, RELAP5/MOD2, N2 - Simulators of this type are used for training and maintaining competence to ensure the safe and reliable operation of nuclear power plants throughout the world. In this study the response of the modernized Krko nuclear power plant (NPP) to a total-loss-of-feedwater accident, leading to the total loss of the secondary heat sink, was calculated. Based on these results, the validation of the full-scope simulator was performed. The verified plant-specific RELAP5/MOD2 input model of the Krko NPP, adapted for the 2000 MWt power (cycle 17), including the model for replacement steam generators, was used. Core heatup occurred in the analyzed case. Core degradation and melting are outside the scope of the RELAP5/MOD2 best-estimate code simulation, but it can predict all the events up to the moment when the core cladding temperature starts to approach the melting point. The comparison of the Krko full-scope simulator (KFSS) data with the calculated reference data shows good agreement and indicates that the simulator-validation testing for this kind of accident was successful. UR - https://www.sv-jme.eu/sl/article/simulation-of-a-hypothetical-loss-of-feedwater-accident-in-a-modernized-nuclear-power-plant/
Parzer, Iztok, AND Mavko, Borut. "Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant" Strojniški vestnik - Journal of Mechanical Engineering [Online], Volume 49 Number 9 (07 July 2017)
Strojniški vestnik - Journal of Mechanical Engineering 49(2003)9, 430-444
© The Authors, CC-BY 4.0 Int. Change in copyright policy from 2022, Jan 1st.
Simulators of this type are used for training and maintaining competence to ensure the safe and reliable operation of nuclear power plants throughout the world. In this study the response of the modernized Krko nuclear power plant (NPP) to a total-loss-of-feedwater accident, leading to the total loss of the secondary heat sink, was calculated. Based on these results, the validation of the full-scope simulator was performed. The verified plant-specific RELAP5/MOD2 input model of the Krko NPP, adapted for the 2000 MWt power (cycle 17), including the model for replacement steam generators, was used. Core heatup occurred in the analyzed case. Core degradation and melting are outside the scope of the RELAP5/MOD2 best-estimate code simulation, but it can predict all the events up to the moment when the core cladding temperature starts to approach the melting point. The comparison of the Krko full-scope simulator (KFSS) data with the calculated reference data shows good agreement and indicates that the simulator-validation testing for this kind of accident was successful.