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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

Not Available

Sponsoring Organization:
USDOE
OSTI ID:
1632055
Journal Information:
Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: C Vol. 365; ISSN 0029-5493
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English

References (8)

Hot channel factors for rod temperature calculations in LMFBR assemblies journal December 1980
Simulation of turbulent flow inside different subchannels in tight lattice bundle journal November 2011
Stability enhancement of planar transport solution based whole-core calculation employing augmented axial method of characteristics journal August 2020
Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT journal December 2016
Numerical simulation of flows in tight-lattice fuel bundles journal July 2008
A consistent 2D/1D approximation to the 3D neutron transport equation journal December 2015
Spectral element applications in complex nuclear reactor geometries: Tet-to-hex meshing journal February 2020
Applications of SHARP Toolkit to SFR Challenging Problems: Evaluation of Hot Channel Factors and Demonstration of Zooming Capability report September 2018

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