Thermal–hydraulic analysis of wire-wrapped SFR test subassemblies by subchannel analysis method
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference19 articles.
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3. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles – bundle friction factors, subchannel friction factors and mixing parameters;Cheng;Nuclear Engineering and Design,1986
4. Laminar, transition and turbulent parallel flow pressure drop across wire-wrap-spaced rod bundle;Engel;Nuclear Science and Engineering,1979
5. Temperature distribution in the duct wall and at the exit of a 19-rod simulated LMFBR fuel assembly (FFM Bundle 2A);Fontana;Nuclear Technology,1974
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