Experimental study of the flow characteristics in an SFR type 61-pin rod bundle using iso-kinetic sampling method
- 19 April 2017
- journal article
- Published by Elsevier BV in Annals of Nuclear Energy
- Vol. 106, 160-169
- https://doi.org/10.1016/j.anucene.2017.03.024
Abstract
No abstract availableKeywords
Funding Information
- National Research Foundation
- NRF
- MSIP (2012M2A8A2025638)
This publication has 12 references indexed in Scilit:
- Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast ReactorNuclear Engineering and Technology, 2016
- Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundlesNuclear Engineering and Design, 2014
- A FLOW AND PRESSURE DISTRIBUTION OF APR+ REACTOR UNDER THE 4-PUMP RUNNING CONDITIONS WITH A BALANCED FLOW RATENuclear Engineering and Technology, 2012
- A subchannel analysis code MATRA-LMR for wire wrapped LMR subassemblyAnnals of Nuclear Energy, 2002
- Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parametersNuclear Engineering and Design, 1986
- Coolant mixing and subchannel velocities in an LMFBR fuel assemblyNuclear Engineering and Design, 1977
- A porous body model for predicting temperature distribution in wire-wrapped fuel rod assembliesNuclear Engineering and Design, 1975
- Forced-flow interchannel mixing model for fuel rod assemblies utilizing a helical wire-wrap spacer systemNuclear Engineering and Design, 1972
- Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire-wrap spacer systemNuclear Engineering and Design, 1972
- Use of Hydraulic Models in Nuclear Reactor DesignNuclear Science and Engineering, 1967