Two-Phase CFD Study of Coolant through a 5×5 Rod Bundles with Grid Spacers

Abstract:

A numerical study using computational fluid dynamics (CFD) under air/water two-phase flow condition without thermal transmission is carried out utilizing the commercial CFD code CFX. A detailed geometry of 5×5 rod bundles with two grid spacers in the Pressurized Water Reactor (PWR) is set up for analyzing. The Multiple Size Group (MUSIG) model based on the population balance equation is employed to describe the characteristic of flow field in which the dispersed phase has a large variation in size, and the breakup and coalescence interaction among different sizes of the bubbles. The effects of the size fraction at inlet, the size group quantities, the breakup and coalescence coefficients, the momentum transfer model, and so on, are studied. The results demonstrate that various parameters and two-phase model have different impacts on the analysis results. The detailed CFD modeling methodology for two-phase flow conditions in PWR fuel assemblies is developed according to the above-mentioned investigations. The flow field patterns and air/water phase distributions in the computational results shows that the two-phase modeling methodology in the present work is reasonable.

• Periodical: Applied Mechanics and Materials (Volumes 444-445)
• Pages: 529-533
• DOI: https://doi.org/10.4028/www.scientific.net/AMM.444-445.529
• Online since: October 2013
• Authors: Shen Gen Tan, Song Wei Li, Yong Jun Jiao, Qing Lu, Guo Bin Wang, Zheng Yu Wang
• Keywords: CFD, Grid Spacers, MUSIG, Two-Phase

References

[1] Julian S.C. Chiang, Bau-Shei Pei, F. Peter Tsai , Pressurized water reactor (PWR) hot-leg streaming. Part 1: Computational fluid dynamics (CFD) simulations. Nucl. Eng. Des., (2010)1-8.

[2] C.Y. Wu, Y.M. Ferng, C.C. Chieng, Z.C. Kang, CFD analysis for full vessel upper plenum in Maanshan Nuclear Power Plant, Nucl. Eng. Des., 253, (2012)285-293.

DOI: 10.1016/j.nucengdes.2012.08.014

[3] Min-Tsung Kao , Chung-Yun Wu, CFD analysis of PWR core top and reactor vessel upper plenum internal subdomain models, Nucl. Eng. Des., 241, (2011)4181-4193.

DOI: 10.1016/j.nucengdes.2011.08.007

[4] F. Hofmann, F. Archambeau, C. Chaize, Computational fluid dynamic analysis of a guide tube in a PWR, Nucl. Eng. Des., 200, (2000)117-126.

DOI: 10.1016/s0029-5493(99)00322-2

[5] Michael E. Conner, Emilio Baglietto, Abdelaziz M. Elmahdi, CFD methodology and validation for single-phase flow in PWR fuel assemblies, Nucl. Eng. Des., 240 (2010) 2088-(2095).

DOI: 10.1016/j.nucengdes.2009.11.031

[6] Luo, S.M., Svendsen H, Theoretical for drop and bubble breakup in turbulent dispersions, AICHE Journal 42, 1225-1233.

DOI: 10.1002/aic.690420505

[7] Prince. M., Blanch. H., Bubble coalescence and break-up in air-sparged bubble colums, AICHE Journal 36, 1485-1499.

DOI: 10.1002/aic.690361004