Development of a Wide-Range Pre-CHF Convective Boiling Correlation

Aounallah, Y.

doi:10.1080/18811248.2010.9711966

Cited by 1 publication

(2 citation statements)

References 8 publications

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“…Both Jens-Lottes correlation and Thom correlation cover typical PWR-type conditions. However, since Thom correlation is capable of calculating the coolant heat transfer coefficient in both subcooled boiling regime and saturated boiling regime (Aounallah, 2010), it could serve as a transitional correlation between two regimes. Therefore, it was adopted in this work.…”

Section: Subcooled Boiling Regimementioning

confidence: 99%

“…Both Schrock-Grossman correlation and Chen correlation are suitable for the simulation in this region. However, since Schrock-Grossman correlation has a more concise expression and is well performed at low and intermediate pressure ranges (Aounallah, 2010), it was adopted in this work to calculate the coolant heat transfer coefficient in this regime (Schrock and Grossman, 1962), which is given by…”

Section: Saturated Boiling Regimementioning

confidence: 99%

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Multiphysics Investigation on Coolant Thermohydraulic Conditions and Fuel Rod Behavior During a Loss-of-Coolant Accident

Yu¹,

Qian

Zhou

2021

Front. Energy Res.

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This article simulates the multiphysics coolant thermohydraulic conditions and fuel performance of a pressurized water reactor (PWR) during a loss-of-coolant accident (LOCA). In the coolant channel of a PWR, the coolant undergoes a series of different boiling regimes along the axial direction. At the inlet of the coolant channel, heat exchange between the cladding wall and coolant is based on single-phase forced convection. As the coolant flow distance increases, the boiling regime gradually converts to nucleate boiling. When a LOCA occurs, on the one hand, the coolant flux and coolant pressure decrease sharply; on the other hand, the heat flux at the cladding wall decreases relatively slowly. They both contribute to a swift increase in coolant temperature. As a consequence, a boiling crisis may occur as critical heat flux (CHF) decreases. In this article, the void fraction along the length of coolant channel in a reactor and mechanical performance of Zr cladding enwrapping UO2 fuel are investigated by establishing a fully coupled multiphysics model based on the CAMPUS code. Physical models of coolant boiling regimes are implemented into the CAMPUS code by adopting different heat transfer models and void fraction models. Physical properties of the coolant are implemented into the CAMPUS code using curve-fitting results. All physical models and parameters related to solid heat transfer are implemented into the CAMPUS code with a 2D axisymmetric geometry. The modeling results help enhance our understanding of void fraction along the length of the coolant channel and mechanical performance of Zr cladding enwrapping UO2 fuel under different coolant pressure and mass flux conditions during a LOCA.

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Section: Subcooled Boiling Regimementioning

confidence: 99%

Section: Saturated Boiling Regimementioning

confidence: 99%