Computational analysis of two-phase flow in horizontal bundles

Carver, Michael; Tahir, A.; Rowe, D.S.; Tapucu, A.; Ahmad, S.Y.

doi:10.1016/0029-5493(84)90213-9

Cited by 9 publications

(1 citation statement)

References 6 publications

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“…Applications of CFD for the prediction of two-phase flow velocity, sub-cooled boiling for void distribution in Krepper et al (2007b). Analyses extended in the rod bundle (Carver et al, 1984;Anglart and Nylund, 1996). The CFD approach permits the feasibility of modelling complicated flow field consisting of a spacer grid and a rod bundle and to evaluate the local velocity and enthalpy distribution around the rod surface, which can be taken as the initial conditions for the onset development of the two-phase structure or for improved CNF performance.…”

Section: Review Of Models and Methods For Two-phase Flowmentioning

confidence: 99%

Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges

Yeoh

2019

Exp. Comput. Multiph. Flow

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Thermal hydraulic analysis of nuclear reactor core and its associated systems can be performed using analysis system, subchannel or computational fluid dynamics (CFD) codes to estimate the different thermal hydraulic safety margins. The safety margins and operating power limits under different conditions of the primary as well as secondary cooling system such as the system pressure, coolant inlet temperature, coolant flow rate, and thermal power and its distributions are considered as key parameters for thermal hydraulic analysis. Considering the complexity of rod bundle geometry, boiling heat transfer and different turbulent scales bring about the many challenges in performing the thermal hydraulic analysis to ensure the safe design and operation of nuclear reactor systems under normal and abnormal conditions. A comprehensive review is presented of past, present and future challenges in state-of-the-art thermal hydraulic analysis covering various aspects of experimental, analytical and computational approaches.

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Section: Review Of Models and Methods For Two-phase Flowmentioning

confidence: 99%