Horizontal steam generator thermal-hydraulics at various steady-state power levels
Само за регистроване кориснике
2002
Конференцијски прилог (Објављена верзија)
Метаподаци
Приказ свих података о документуАпстракт
Three-dimensional computer simulation and analyses of the horizontal steam generator thermal-hydraulics of the WWER 1000 nuclear power plant have been performed for 50% and 75% partial loads, 100% nominal load and 110% over-load. Presented results show water and steam mass flow rate vectors, steam void fraction spatial distribution, recirculation zones, swell level position, water mass inventory on the shell side, and other important thermal-hydraulic parameters. The simulations have been performed with the computer code 3D ANA, based on the "two-fluid" model approach. Steam-water interface transport processes, as well as tube bundle flow resistance, energy transfer, and steam generation within tube bundles are modelled with "closure laws". Applied approach implies non-equilibrium thermal and flow conditions. The model is solved by the control volume procedure, which has been extended in order to take into account the 3D flow of liquid and gas phase. The methodology is validated by com...paring numerical and experimental results of real steam generator operational conditions at various power levels of the WWER Novovoronezh, Unit 5. One-dimensional model of the horizontal steam generator has been built with the RELAP 5 standard code on the basis of the multidimensional two-phase flow structure obtained with the 3D ANA code. RELAP 5 and 3D ANA code results are compared, showing acceptable agreement.
Извор:
International Conference on Nuclear Engineering, Proceedings, ICONE, 2002, 3, 767-779Колекције
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/123456789/253 AB - Three-dimensional computer simulation and analyses of the horizontal steam generator thermal-hydraulics of the WWER 1000 nuclear power plant have been performed for 50% and 75% partial loads, 100% nominal load and 110% over-load. Presented results show water and steam mass flow rate vectors, steam void fraction spatial distribution, recirculation zones, swell level position, water mass inventory on the shell side, and other important thermal-hydraulic parameters. The simulations have been performed with the computer code 3D ANA, based on the "two-fluid" model approach. Steam-water interface transport processes, as well as tube bundle flow resistance, energy transfer, and steam generation within tube bundles are modelled with "closure laws". Applied approach implies non-equilibrium thermal and flow conditions. The model is solved by the control volume procedure, which has been extended in order to take into account the 3D flow of liquid and gas phase. The methodology is validated by comparing numerical and experimental results of real steam generator operational conditions at various power levels of the WWER Novovoronezh, Unit 5. One-dimensional model of the horizontal steam generator has been built with the RELAP 5 standard code on the basis of the multidimensional two-phase flow structure obtained with the 3D ANA code. RELAP 5 and 3D ANA code results are compared, showing acceptable agreement. C3 - International Conference on Nuclear Engineering, Proceedings, ICONE T1 - Horizontal steam generator thermal-hydraulics at various steady-state power levels EP - 779 SP - 767 VL - 3 DO - 10.1115/ICONE10-22451 ER -
@conference{ author = "Stevanović, Vladimir and Stošić, Zoran V. and Kiera, M. and Stoll, Uwe", year = "2002", abstract = "Three-dimensional computer simulation and analyses of the horizontal steam generator thermal-hydraulics of the WWER 1000 nuclear power plant have been performed for 50% and 75% partial loads, 100% nominal load and 110% over-load. Presented results show water and steam mass flow rate vectors, steam void fraction spatial distribution, recirculation zones, swell level position, water mass inventory on the shell side, and other important thermal-hydraulic parameters. The simulations have been performed with the computer code 3D ANA, based on the "two-fluid" model approach. Steam-water interface transport processes, as well as tube bundle flow resistance, energy transfer, and steam generation within tube bundles are modelled with "closure laws". Applied approach implies non-equilibrium thermal and flow conditions. The model is solved by the control volume procedure, which has been extended in order to take into account the 3D flow of liquid and gas phase. The methodology is validated by comparing numerical and experimental results of real steam generator operational conditions at various power levels of the WWER Novovoronezh, Unit 5. One-dimensional model of the horizontal steam generator has been built with the RELAP 5 standard code on the basis of the multidimensional two-phase flow structure obtained with the 3D ANA code. RELAP 5 and 3D ANA code results are compared, showing acceptable agreement.", journal = "International Conference on Nuclear Engineering, Proceedings, ICONE", title = "Horizontal steam generator thermal-hydraulics at various steady-state power levels", pages = "779-767", volume = "3", doi = "10.1115/ICONE10-22451" }
Stevanović, V., Stošić, Z. V., Kiera, M.,& Stoll, U.. (2002). Horizontal steam generator thermal-hydraulics at various steady-state power levels. in International Conference on Nuclear Engineering, Proceedings, ICONE, 3, 767-779. https://doi.org/10.1115/ICONE10-22451
Stevanović V, Stošić ZV, Kiera M, Stoll U. Horizontal steam generator thermal-hydraulics at various steady-state power levels. in International Conference on Nuclear Engineering, Proceedings, ICONE. 2002;3:767-779. doi:10.1115/ICONE10-22451 .
Stevanović, Vladimir, Stošić, Zoran V., Kiera, M., Stoll, Uwe, "Horizontal steam generator thermal-hydraulics at various steady-state power levels" in International Conference on Nuclear Engineering, Proceedings, ICONE, 3 (2002):767-779, https://doi.org/10.1115/ICONE10-22451 . .