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Title: CFD Simulations of a Flow Mixing and Heat Transfer Enhancement in an Advanced LWR Nuclear Fuel Assembly

A computational fluid dynamics (CFD) analysis has been performed to investigate a flow-mixing and heat-transfer enhancement caused by a mixing-vane spacer in a LWR fuel assembly which is a rod bundle. This paper presents the CFD simulations of a flow mixing and heat transfer in a fully heated 5x5 array of a rod bundle with a split-vane and hybrid-vane spacer. The CFD prediction at a low Reynolds number of 42,000 showed a reasonably good agreement of the initial heat transfer enhancement with the measured one for a partially heated experiment using a similar spacer structure. The CFD simulation also predicted the decay rate of a normalized Nusselt number downstream of the split-vane spacer which agrees fairly well with those of the experiment and the correlation. The CFD calculations for the split vane and hybrid vane at the LWR operating conditions(Re = 500,000) predicted hot fuel spots in a streaky structure downstream of the spacer, which occurs due to the secondary flow occurring in an opposite direction near the fuel rod. However, the split-vane and hybrid-vane spacers are predicted to significantly enhance the overall heat transfer of a LWR nuclear fuel assembly. (authors)
Authors:
; ; ;  [1]
  1. Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong-Gu, Daejeon, Korea 305-353 (Korea, Republic of)
Publication Date:
OSTI Identifier:
21229264
Resource Type:
Conference
Resource Relation:
Conference: 2007 LWR Fuel Performance Meeting / TopFuel 2007, San Francisco, CA (United States), 30 Sep - 3 Oct 2007; Other Information: Country of input: France; 12 refs; Related Information: In: Proceedings of the 2007 LWR Fuel Performance Meeting / TopFuel 2007 'Zero by 2010', 683 pages.
Publisher:
American Nuclear Society - ANS, La Grange Park (United States)
Research Org:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; COMPUTERIZED SIMULATION; FLUID MECHANICS; FUEL ELEMENT CLUSTERS; FUEL RODS; HEAT TRANSFER; HYBRIDIZATION; NUCLEAR FUELS; NUSSELT NUMBER; REYNOLDS NUMBER