This paper examines the influence of High Temperature Gas-cooled Reactor (HTGR) module power rating and normal operating temperatures on the use of SA508/533 material for the HTGR vessel system with emphasis on the calculated times at elevated temperatures approaching or exceeding ASME Code Service Limits (Levels B&C) to which the reactor pressure vessel could be exposed during postulated pressurized and depressurized conduction cooldown events over its design lifetime
The high-temperature gas-cooled nuclear reactor (HTGR) is an attractive potential source of primary ...
The High Temperature Reactor (HTR) is an advanced reactor concept with particular safety features. F...
The operational safety of nuclear power plants remains among the main issues affecting the acceptanc...
Current interest expressed by industry in HTGR plants, particularly modular plants with power up to ...
Analyses were performed to determine maximum temperatures in the reactor pressure vessel for two pot...
The project supported the Nuclear Regulatory Commission (NRC) in identifying and evaluating the regu...
The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], an...
In 1999, an international collaborative initiative for the development of advanced (Generation IV) r...
In 1999, an international collaborative initiative for the development of advanced (Generation IV) r...
In 1999, an international collaborative initiative for the development of advanced (Generation IV) r...
The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) desi...
This paper presents the approach used to define the technology program needed to support design and ...
The report deals with two special questions for gas-cooled high-temperature reactors of modular desi...
The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant ...
An assessment of the HTGR opportunities from the year 2000 through 2045 was the principal activity o...
The high-temperature gas-cooled nuclear reactor (HTGR) is an attractive potential source of primary ...
The High Temperature Reactor (HTR) is an advanced reactor concept with particular safety features. F...
The operational safety of nuclear power plants remains among the main issues affecting the acceptanc...
Current interest expressed by industry in HTGR plants, particularly modular plants with power up to ...
Analyses were performed to determine maximum temperatures in the reactor pressure vessel for two pot...
The project supported the Nuclear Regulatory Commission (NRC) in identifying and evaluating the regu...
The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], an...
In 1999, an international collaborative initiative for the development of advanced (Generation IV) r...
In 1999, an international collaborative initiative for the development of advanced (Generation IV) r...
In 1999, an international collaborative initiative for the development of advanced (Generation IV) r...
The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) desi...
This paper presents the approach used to define the technology program needed to support design and ...
The report deals with two special questions for gas-cooled high-temperature reactors of modular desi...
The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant ...
An assessment of the HTGR opportunities from the year 2000 through 2045 was the principal activity o...
The high-temperature gas-cooled nuclear reactor (HTGR) is an attractive potential source of primary ...
The High Temperature Reactor (HTR) is an advanced reactor concept with particular safety features. F...
The operational safety of nuclear power plants remains among the main issues affecting the acceptanc...
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