Numerical simulation and analyses of the loss of feedwater transient at the unit 4 of KOLA NPP
Само за регистроване кориснике
2002
Конференцијски прилог (Објављена верзија)
Метаподаци
Приказ свих података о документуАпстракт
A three-dimensional numerical simulation of the loss-of-feed water transient at the horizontal steam generator of the Kola nuclear power plant is performed. Presented numerical results show transient change of integral steam generator parameters, such as steam generation rate, water mass inventory, outlet reactor coolant temperature, as well as detailed distribution of shell side thermal-hydraulic parameters: swell and collapsed levels, void fraction distributions, mass flux vectors, etc. Numerical results are compared with measurements at the Kola NPP. The agreement is satisfactory, while differences are close to or below the measurement uncertainties. Obtained numerical results are the first ones that give complete insight into the three-dimensional and transient horizontal steam generator thermal-hydraulics. Also, the presented results serve as benchmark tests for the assessment and further improvement of one-dimensional models of horizontal steam generator built with safety codes.
Извор:
International Conference on Nuclear Engineering, Proceedings, ICONE, 2002, 3, 781-792Колекције
Институција/група
Mašinski fakultetTY - CONF AU - Stevanović, Vladimir AU - Stošić, Zoran V. AU - Kiera, M. AU - Stoll, Uwe PY - 2002 UR - https://machinery.mas.bg.ac.rs/handle/123456789/251 AB - A three-dimensional numerical simulation of the loss-of-feed water transient at the horizontal steam generator of the Kola nuclear power plant is performed. Presented numerical results show transient change of integral steam generator parameters, such as steam generation rate, water mass inventory, outlet reactor coolant temperature, as well as detailed distribution of shell side thermal-hydraulic parameters: swell and collapsed levels, void fraction distributions, mass flux vectors, etc. Numerical results are compared with measurements at the Kola NPP. The agreement is satisfactory, while differences are close to or below the measurement uncertainties. Obtained numerical results are the first ones that give complete insight into the three-dimensional and transient horizontal steam generator thermal-hydraulics. Also, the presented results serve as benchmark tests for the assessment and further improvement of one-dimensional models of horizontal steam generator built with safety codes. C3 - International Conference on Nuclear Engineering, Proceedings, ICONE T1 - Numerical simulation and analyses of the loss of feedwater transient at the unit 4 of KOLA NPP EP - 792 SP - 781 VL - 3 DO - 10.1115/ICONE10-22452 ER -
@conference{ author = "Stevanović, Vladimir and Stošić, Zoran V. and Kiera, M. and Stoll, Uwe", year = "2002", abstract = "A three-dimensional numerical simulation of the loss-of-feed water transient at the horizontal steam generator of the Kola nuclear power plant is performed. Presented numerical results show transient change of integral steam generator parameters, such as steam generation rate, water mass inventory, outlet reactor coolant temperature, as well as detailed distribution of shell side thermal-hydraulic parameters: swell and collapsed levels, void fraction distributions, mass flux vectors, etc. Numerical results are compared with measurements at the Kola NPP. The agreement is satisfactory, while differences are close to or below the measurement uncertainties. Obtained numerical results are the first ones that give complete insight into the three-dimensional and transient horizontal steam generator thermal-hydraulics. Also, the presented results serve as benchmark tests for the assessment and further improvement of one-dimensional models of horizontal steam generator built with safety codes.", journal = "International Conference on Nuclear Engineering, Proceedings, ICONE", title = "Numerical simulation and analyses of the loss of feedwater transient at the unit 4 of KOLA NPP", pages = "792-781", volume = "3", doi = "10.1115/ICONE10-22452" }
Stevanović, V., Stošić, Z. V., Kiera, M.,& Stoll, U.. (2002). Numerical simulation and analyses of the loss of feedwater transient at the unit 4 of KOLA NPP. in International Conference on Nuclear Engineering, Proceedings, ICONE, 3, 781-792. https://doi.org/10.1115/ICONE10-22452
Stevanović V, Stošić ZV, Kiera M, Stoll U. Numerical simulation and analyses of the loss of feedwater transient at the unit 4 of KOLA NPP. in International Conference on Nuclear Engineering, Proceedings, ICONE. 2002;3:781-792. doi:10.1115/ICONE10-22452 .
Stevanović, Vladimir, Stošić, Zoran V., Kiera, M., Stoll, Uwe, "Numerical simulation and analyses of the loss of feedwater transient at the unit 4 of KOLA NPP" in International Conference on Nuclear Engineering, Proceedings, ICONE, 3 (2002):781-792, https://doi.org/10.1115/ICONE10-22452 . .