PREDICTION OF SWELL LEVEL AND WATER MASS INVENTORY IN STEAM GENERATORS
Само за регистроване кориснике
2013
Конференцијски прилог (Објављена верзија)
Метаподаци
Приказ свих података о документуАпстракт
A prediction of steam generator behaviour in case of a loss-of-feedwater transient
and a calculation of a time period in which tubes’ dry out will occur, strongly
depends on an initial water mass inventory on the secondary side of the steam
generator and a two-phase mixture swell level. A reliable prediction of the swell
level and water mass inventory is based on appropriate interfacial drag force
correlations or steam-water slip models and a robust numerical method that is able
to predict the swell level movement. A prior assumption of the swell level fixed
position in a thermal-hydraulic simulation of the steam generator secondary side
might lead to erroneous results. In this paper the prediction of the two-phase flow
around tubes in a bundle and the calculation of the steam generator secondary side
thermal-hydraulics is based on the two-fluid model and the Computational Multi
Fluid Dynamics (CMFD) approach. The applied approach solves the vapourliquid
multidim...ensional two-phase flow and it enables the determination of the
swell level position and corresponding liquid mass inventory. Vapour and liquid
interfacial mass, momentum and energy transfers are modelled with the closure
laws, where some of them are specially developed for the condition of two-phase
flow across tube bundles. The governing equations are solved by the SIMPLE
type pressure-correction method that is derived for the multiphase flow
conditions. The developed model is applied to the prediction of experimental
conditions of refrigerant R113 boiling around tubes in a bundle at the atmospheric
pressure. The numerically calculated swell level and the pressure field in the two
phase mixture are compared with available measured data and a good agreement
is achieved, which also indicates a good prediction of the vapour void fraction and
liquid mass inventory. The developed numerical method and performed
simulations are an improvement regarding previous investigations that were based
on the calculation with the fixed swell level and without the validation of the
water mass inventory on the steam generator secondary side.
Извор:
Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics (NURETH-15), Pisa, Italy, May 12-17, 2013, 2013, NURETH15-369-Издавач:
- Nuclear Research Group of San Piero a Grado (GRNSPG) of the University of Pisa (UNIPI), the Nuclear and INdustrial Engineering (NINE) and the Thermalhydraulics Division of the American Nuclear Society (ANS)
Финансирање / пројекти:
- Напредне аналитичке, нумеричке и методе анализе примењене механике флуида и комплексних система (RS-174014)
Колекције
Институција/група
Mašinski fakultetTY - CONF AU - Maslovarić, Blaženka AU - Stevanović, Vladimir AU - Milivojević, Sanja PY - 2013 UR - https://machinery.mas.bg.ac.rs/handle/123456789/4502 AB - A prediction of steam generator behaviour in case of a loss-of-feedwater transient and a calculation of a time period in which tubes’ dry out will occur, strongly depends on an initial water mass inventory on the secondary side of the steam generator and a two-phase mixture swell level. A reliable prediction of the swell level and water mass inventory is based on appropriate interfacial drag force correlations or steam-water slip models and a robust numerical method that is able to predict the swell level movement. A prior assumption of the swell level fixed position in a thermal-hydraulic simulation of the steam generator secondary side might lead to erroneous results. In this paper the prediction of the two-phase flow around tubes in a bundle and the calculation of the steam generator secondary side thermal-hydraulics is based on the two-fluid model and the Computational Multi Fluid Dynamics (CMFD) approach. The applied approach solves the vapourliquid multidimensional two-phase flow and it enables the determination of the swell level position and corresponding liquid mass inventory. Vapour and liquid interfacial mass, momentum and energy transfers are modelled with the closure laws, where some of them are specially developed for the condition of two-phase flow across tube bundles. The governing equations are solved by the SIMPLE type pressure-correction method that is derived for the multiphase flow conditions. The developed model is applied to the prediction of experimental conditions of refrigerant R113 boiling around tubes in a bundle at the atmospheric pressure. The numerically calculated swell level and the pressure field in the two phase mixture are compared with available measured data and a good agreement is achieved, which also indicates a good prediction of the vapour void fraction and liquid mass inventory. The developed numerical method and performed simulations are an improvement regarding previous investigations that were based on the calculation with the fixed swell level and without the validation of the water mass inventory on the steam generator secondary side. PB - Nuclear Research Group of San Piero a Grado (GRNSPG) of the University of Pisa (UNIPI), the Nuclear and INdustrial Engineering (NINE) and the Thermalhydraulics Division of the American Nuclear Society (ANS) C3 - Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics (NURETH-15), Pisa, Italy, May 12-17, 2013 T1 - PREDICTION OF SWELL LEVEL AND WATER MASS INVENTORY IN STEAM GENERATORS SP - NURETH15-369 UR - https://hdl.handle.net/21.15107/rcub_machinery_4502 ER -
@conference{ author = "Maslovarić, Blaženka and Stevanović, Vladimir and Milivojević, Sanja", year = "2013", abstract = "A prediction of steam generator behaviour in case of a loss-of-feedwater transient and a calculation of a time period in which tubes’ dry out will occur, strongly depends on an initial water mass inventory on the secondary side of the steam generator and a two-phase mixture swell level. A reliable prediction of the swell level and water mass inventory is based on appropriate interfacial drag force correlations or steam-water slip models and a robust numerical method that is able to predict the swell level movement. A prior assumption of the swell level fixed position in a thermal-hydraulic simulation of the steam generator secondary side might lead to erroneous results. In this paper the prediction of the two-phase flow around tubes in a bundle and the calculation of the steam generator secondary side thermal-hydraulics is based on the two-fluid model and the Computational Multi Fluid Dynamics (CMFD) approach. The applied approach solves the vapourliquid multidimensional two-phase flow and it enables the determination of the swell level position and corresponding liquid mass inventory. Vapour and liquid interfacial mass, momentum and energy transfers are modelled with the closure laws, where some of them are specially developed for the condition of two-phase flow across tube bundles. The governing equations are solved by the SIMPLE type pressure-correction method that is derived for the multiphase flow conditions. The developed model is applied to the prediction of experimental conditions of refrigerant R113 boiling around tubes in a bundle at the atmospheric pressure. The numerically calculated swell level and the pressure field in the two phase mixture are compared with available measured data and a good agreement is achieved, which also indicates a good prediction of the vapour void fraction and liquid mass inventory. The developed numerical method and performed simulations are an improvement regarding previous investigations that were based on the calculation with the fixed swell level and without the validation of the water mass inventory on the steam generator secondary side.", publisher = "Nuclear Research Group of San Piero a Grado (GRNSPG) of the University of Pisa (UNIPI), the Nuclear and INdustrial Engineering (NINE) and the Thermalhydraulics Division of the American Nuclear Society (ANS)", journal = "Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics (NURETH-15), Pisa, Italy, May 12-17, 2013", title = "PREDICTION OF SWELL LEVEL AND WATER MASS INVENTORY IN STEAM GENERATORS", pages = "NURETH15-369", url = "https://hdl.handle.net/21.15107/rcub_machinery_4502" }
Maslovarić, B., Stevanović, V.,& Milivojević, S.. (2013). PREDICTION OF SWELL LEVEL AND WATER MASS INVENTORY IN STEAM GENERATORS. in Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics (NURETH-15), Pisa, Italy, May 12-17, 2013 Nuclear Research Group of San Piero a Grado (GRNSPG) of the University of Pisa (UNIPI), the Nuclear and INdustrial Engineering (NINE) and the Thermalhydraulics Division of the American Nuclear Society (ANS)., NURETH15-369. https://hdl.handle.net/21.15107/rcub_machinery_4502
Maslovarić B, Stevanović V, Milivojević S. PREDICTION OF SWELL LEVEL AND WATER MASS INVENTORY IN STEAM GENERATORS. in Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics (NURETH-15), Pisa, Italy, May 12-17, 2013. 2013;:NURETH15-369. https://hdl.handle.net/21.15107/rcub_machinery_4502 .
Maslovarić, Blaženka, Stevanović, Vladimir, Milivojević, Sanja, "PREDICTION OF SWELL LEVEL AND WATER MASS INVENTORY IN STEAM GENERATORS" in Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics (NURETH-15), Pisa, Italy, May 12-17, 2013 (2013):NURETH15-369, https://hdl.handle.net/21.15107/rcub_machinery_4502 .