Investigation on subchannel flow distribution in wire-wrapped 37 and 61-pin bundle using computational fluid dynamics
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Title
Investigation on subchannel flow distribution in wire-wrapped 37 and 61-pin bundle using computational fluid dynamics
Authors
Keywords
Sodium-cooled fast reactor, Wire-wrapped fuel bundle, Friction factor, Flow split factor, Computational fluid dynamics
Journal
NUCLEAR ENGINEERING AND DESIGN
Volume 370, Issue -, Pages 110904
Publisher
Elsevier BV
Online
2020-11-03
DOI
10.1016/j.nucengdes.2020.110904
References
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Related references
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- Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor
- (2016) Seok-Kyu Chang et al. Nuclear Engineering and Technology
- CFD investigations of helical wire-wrap fuel pin bundle and its comparison with straight wire bundle
- (2016) R. Gajapathy et al. PROGRESS IN NUCLEAR ENERGY
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- (2011) E. Merzari et al. NUCLEAR ENGINEERING AND DESIGN
- DEVELOPMENT OF THE MATRA-LMR-FB FOR FLOW BLOCKAGE ANALYSIS IN A LMR
- (2011) Kwi-Seok Ha et al. Nuclear Engineering and Technology
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