Verification and Validation of Spectral Element Code for Supercritical CO2 Flow in Vertical Heated Tubes

Author:

Yuan Haomin1ORCID,Nguyen Tri2,Merzari Elia12,Shaver Dillon1,Tomboulides Ananias3

Affiliation:

1. Argonne National Laboratory, Nuclear Science and Engineering Division, Lemont, Illinois

2. The Pennsylvania State University, Ken and Mary Alice Lindquist Department of Nuclear Engineering, University Park, Pennsylvania 16802

3. Aristotle University of Thessaloniki, Department of Mechanical Engineering, Thessaloniki 541 24, Greece

Funder

Nuclear Energy Advanced Modeling and Simulation

Publisher

Informa UK Limited

Reference35 articles.

1. V. DOSTAL M. J. DRISCOLL and P. HEJZLAR “A Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors ” MIT-ANP-TR-100 Advanced Nuclear Power Technology Program MIT Center for Advanced Nuclear Energy Systems (2004).

2. Deterioration in Heat Transfer to Fluids at Supercritical Pressure and High Heat Fluxes

3. Forced Convection Heat Transfer to Fluids at Supercritical Pressure;JACKSON J.;Turbulent Forced Convection Channels Bundles,1979

4. Investigation of Buoyancy Effects on Heat Transfer Characteristics of Supercritical Carbon Dioxide in Heating Mode

5. A. M. KRUIZENGA, “Heat Transfer and Pressure Drop Measurements in Prototypic Heat Exchanges for the Supercritical Carbon Dioxide Brayton Power Cycles,” PhD Thesis, The University of Wisconsin–Madison, Department of Engineering Physics (2010).

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