Author:
Jeong Jae-Ho,Song Min-Seop,Lee Kwi-Lim
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference32 articles.
1. Pressure drop correlations for fuel element spacers;Rehme;Nucl. Technol.,1973
2. Laminar, transition and turbulent parallel flow pressure drop across wire-wrap-spaced rod bundles;Engel;Nucl. Sci. Eng.,1979
3. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles – bundle friction factors, sub-channel friction factors and mixing parameters;Cheng;Nucl. Eng. Des.,1986
4. Flow distribution and pressure loss in subchannels of a wire-wrapped 37-pin rod bundle for a sodium-cooled fast reactor;Chang;Nucl. Eng. Technol.,2016
5. Narita, H., Ohshima, H., 2015. Improvement of single-phase subchannel analysis code ASFRE-III –Verification analysis of fuel pin heat transfer model and pressure loss model, PNC TN9410 97-104.
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