Development of a liquid metal subchannel code applied to ocean conditions and study on the effect of core geometry parameters and ocean motions on flow and heat transfer characteristics
Authors:
- 30 September 2024
- journal article
- research article
- Published by Elsevier in Progress in Nuclear Energy
- Vol. 177
Abstract
No abstract availableKeywords
This publication has 32 references indexed in Scilit:
- Automated core design code development for a lead‐cooled fast reactor and its core optimizationInternational Journal of Energy Research, 2020
- The development and application of a sub-channel code in ocean environmentAnnals of Nuclear Energy, 2016
- Development of a sub-channel code for liquid metal cooled fuel assemblyAnnals of Nuclear Energy, 2015
- A quantitative CFD benchmark for Sodium Fast Reactor fuel assembly modelingAnnals of Nuclear Energy, 2014
- The development and validation of a thermal hydraulic code in rolling motionAnnals of Nuclear Energy, 2011
- An experimental study of pressure drop correlations for wire-wrapped fuel assembliesKSME International Journal, 2001
- 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
- Critical heat flux of forced convection boiling in an oscillating acceleration field — I. General trendsNuclear Engineering and Design, 1982
- Single-phase subchannel mixing in a simulated nuclear fuel assemblyNuclear Engineering and Design, 1974
- Effects of heaving and listing upon thermo-hydraulic performance and critical heat flux of water-cooled marine reactorsNuclear Engineering and Design, 1966