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Title: Evaluation of hot channel factor for sodium-cooled fast reactors with multi-physics toolkit

Journal Article · · Nuclear Engineering and Design

Sponsoring Organization:
USDOE
OSTI ID:
1632055
Journal Information:
Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 365 Journal Issue: C; ISSN 0029-5493
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English
Citation Metrics:
Cited by: 5 works
Citation information provided by
Web of Science

References (6)

Stability enhancement of planar transport solution based whole-core calculation employing augmented axial method of characteristics journal August 2020
Simulation of turbulent flow inside different subchannels in tight lattice bundle journal November 2011
Hot channel factors for rod temperature calculations in LMFBR assemblies journal December 1980
Numerical simulation of flows in tight-lattice fuel bundles journal July 2008
Spectral element applications in complex nuclear reactor geometries: Tet-to-hex meshing journal February 2020
Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT journal December 2016