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Main Results of the Trial Test of a Closed Circuit with Natural Circulation of a Light-Water Coolant under Supercritical Pressure
AbstractMain results are presented of the trial tests of a closed loop with natural circulation (NC) of a light-water coolant under supercritical...
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The Concept of a Nuclear Power Unit on the Basis of a Low-Power Multipurpose Test Research Reactor with Supercritical Light-Water Coolant
AbstractHerein is presented a preliminary concept of a nuclear power installation (NPI) based on a low-power multipurpose test research reactor with...
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Verification of New-Generation Generalizing Correlations and the Results from Predictions and Theoretical Studies on Heat Transfer of Supercritical-Pressure Coolants
Abstract—Heat transfer of supercritical-pressure (SCP) coolants continues to attract the attention of both researchers and engineers. Works on...
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Pseudoboiling
In the area of pressures above the thermodynamic critical \(\left(p>{p}_{c}\right),\)... -
Concept of Pseudo-Boiling
In the area of pressures above the thermodynamic critical $$ \left( {p > p_{c}... -
Heat Transfer Media and Their Properties
This chapter presents a discussion on effect(s) of properties on heat transfer. In general, an impact of a property(ies) on heat transfer depends... -
Heat Transfer Media and Their Properties
This chapter presents a discussion on effect(s) of properties on heat transfer. In general, an impact of a property(ies) on heat transfer depends... -
Prospects for development of an innovative water-cooled nuclear reactor for supercritical parameters of coolant
The state of nuclear power engineering as of February 1, 2014 and the accomplished elaborations of a supercritical-pressure water-cooled reactor are...
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Prospects for development of nuclear power stations equipped with VVER reactors
The prospects for further development in Russia of nuclear stations equipped with water-cooled water-moderated reactors are considered.
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MIF-SKD computation code for thermohydraulic design of a reactor core cooled by supercritical-pressure water
Presented here is the MIF-SKD computation code for channel-by-channel thermohydraulic calculations of fuel-rod assemblies cooled by...
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Problems and prospects of new generation light-water reactors at supercritical pressure
Basic problems in neutron physics, structural materials of fuel rods, and assemblies (FA) for a new generation light-water reactors with...
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The use of supercritical parameters of a coolant—A promising path to development of nuclear power plant water-cooled reactors in the 21st century
A modern concept of the development of water-cooled reactors of nuclear power plants (NPPs) is considered. Data on the design of NPPs with...
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Heat transfer under supercritical pressures and heat transfer deterioration boundaries
Some relations for technical calculations of the normal heat transfer in a rising water flow under supercritical pressure (SCP) are analyzed and...