Thermal-hydraulic analysis of a 7-pin sodium-cooled fast reactor wire-wrapped fuel bundle
Author:
Publisher
Elsevier BV
Subject
Fluid Flow and Transfer Processes,Mechanical Engineering,Condensed Matter Physics
Reference22 articles.
1. CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor;Chen;Ann. Nucl. Energy,2018
2. A summary of sodium-cooled fast reactor development;Aoto;Progress Nucl. Energy,2014
3. Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer;Park;Ann. Nucl. Energy,2018
4. Numerical investigation on thermal-hydraulic characteristics of NaK in a helical wire wrapped annulus;Qin;Int. J. Heat Mass Transf.,2019
5. CFD investigation of helical wire-wrapped 7-pin fuel bundle and the challenges in modeling full scale 217 pin bundle;Gajapathy;Nucl. Eng. Design,2007
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