Search by keyword: "nuclear reactor BREST-OD-300"
Fluid Flow and Mass Transfer in Finned Fuel Rod Assemblies of Nuclear Reactor BREST-OD-300
Authors: Getya S.I., Krapivtsev V.G. , Markov P.V., Solonin V.I. | Published: 09.02.2015 |
Published in issue: #1(100)/2015 | |
DOI: | |
Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
Keywords: nuclear reactor BREST-OD-300, models of fuel rod assemblies, spacing of fuel rods by spiral fins, aerodynamic experiments, computational fluid dynamics, method of heat wake |