The effects of helium pressure on the convection heat transfer coefficient and temperature fields (helium and wall surface temperatures) in a unique scaled-down dual-channel natural circulation loop with upper and lower plena have been investigated in this study. Natural convection is one of the passive safety systems of the prismatic very high-temperature reactors (VHTRs) during the accident scenarios. The operating helium pressure was varied from 413.47 to 689.12 kPa in the temperature range from 6 to 196°C. Radial and axial measurements were carried out along the flow channels using a new sophisticated flush wall-mounted heat transfer coefficient probe in conjunction with the radial adjuster for T-thermocouple that are integrated in a no...
AbstractThe paper presents the results of a computational analysis into the thin-wall sample cooling...
This study investigated how heat transfer occurs during pressurized conduction cooldown accidents (P...
The US Department of Energy, Office of Nuclear Energy (DOE-NE) is supporting the development of a ve...
Natural circulation is considered an important passive safety aspect of the prismatic block gas cool...
Multiphase Reactors Engineering and Applications Laboratory (mReal) at Missouri University of Scienc...
Multiphase Reactors Engineering and Applications Laboratory (mReal) at Missouri University of Scienc...
The prismatic modular reactor (PMR) is one of the leading designs for the next generation of nuclear...
This research focuses on establishing a range of scaled separate and integral effects experiments fo...
A horizontal 2.85 m long, 19 mm i.d. stainless steel heated circular channel was employed to measure...
The use of liquid helium to cool superconducting generators requires an understanding of the effect ...
This study is aimed to obtain fundamental data of transient heat transfer and clarify transient heat...
Multiphase Reactors Engineering and Applications Laboratory (mReal) has designed and constructed a s...
The paper deals with the process properties in terms of the heat transfer, i.e. the thermal performa...
A high temperature and pressure dual-channel facility has been designed and developed at Multiphase ...
Previous findings suggest that natural circulation in simplified geometries cannot be directly exten...
AbstractThe paper presents the results of a computational analysis into the thin-wall sample cooling...
This study investigated how heat transfer occurs during pressurized conduction cooldown accidents (P...
The US Department of Energy, Office of Nuclear Energy (DOE-NE) is supporting the development of a ve...
Natural circulation is considered an important passive safety aspect of the prismatic block gas cool...
Multiphase Reactors Engineering and Applications Laboratory (mReal) at Missouri University of Scienc...
Multiphase Reactors Engineering and Applications Laboratory (mReal) at Missouri University of Scienc...
The prismatic modular reactor (PMR) is one of the leading designs for the next generation of nuclear...
This research focuses on establishing a range of scaled separate and integral effects experiments fo...
A horizontal 2.85 m long, 19 mm i.d. stainless steel heated circular channel was employed to measure...
The use of liquid helium to cool superconducting generators requires an understanding of the effect ...
This study is aimed to obtain fundamental data of transient heat transfer and clarify transient heat...
Multiphase Reactors Engineering and Applications Laboratory (mReal) has designed and constructed a s...
The paper deals with the process properties in terms of the heat transfer, i.e. the thermal performa...
A high temperature and pressure dual-channel facility has been designed and developed at Multiphase ...
Previous findings suggest that natural circulation in simplified geometries cannot be directly exten...
AbstractThe paper presents the results of a computational analysis into the thin-wall sample cooling...
This study investigated how heat transfer occurs during pressurized conduction cooldown accidents (P...
The US Department of Energy, Office of Nuclear Energy (DOE-NE) is supporting the development of a ve...