A Heat Transfer Correlation for Flow Channels in a Prismatic Core VHTR
Author:
Affiliation:
1. Institute for Space and Nuclear Power Studies
2. Chemical and Nuclear Engineering Dept.
3. Mechnical Engineering Dept. University of New Mexico, Albuquerque, NM, 87131, (505) 277-0446, Fax (505) 277-2814, mgenk@unm.edu
Publisher
Informa UK Limited
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST12-A13414
Reference8 articles.
1. Project of the GT-MHR high-temperature helium reactor with gas turbine
2. The gas-turbine modular helium reactor
3. Performance analyses of VHTR plants with direct and indirect closed Brayton cycles and different working fluids
4. Numerical investigation of a heat transfer within the prismatic fuel assembly of a very high temperature reactor
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1. Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor;Journal of Nuclear Engineering and Radiation Science;2015-02-09
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