An air-ingress accident in a VHTR is anticipated to cause severe changes of graphite density and mechanical strength by oxidation process resulting in many side effects. However, the quantitative estimation has not been performed yet. In this study, the focus has been on the prediction of graphite density change and mechanical strength using a thermal hydraulic system analysis code. For analysis of the graphite density change, a simple graphite burn-off model was developed based on the similarity concept between parallel electrical circuit and graphite oxidation considering the overall changes of the graphite geometry and density. The developed model was implemented in the VHTR system analysis code, GAMMA, along with other comprehensive gra...
A primary-pipe break accident is one of the design-basis accidents of a high-temperature gas-cooled ...
Air ingress with graphite burning belongs to the accident scenarios in HTRs with potentially severe ...
In this study, the oxidation characteristics of nuclear grade graphites IG-110, IG-430, Type A(MA), ...
Graphite is used in the gas-cooled nuclear reactors as both a neutron moderator and structural compo...
Dissertation supervisor: Dr. Tushar K. Ghosh nad Dr. Sudarshan K. Loyalka.Includes vita.One of the m...
Doctor of PhilosophyDepartment of Mechanical and Nuclear EngineeringHitesh BindraHelium-cooled, grap...
The U.S. Department of Energy is performing research and development that focuses on key phenomena t...
The US Department of Energy is performing research and development (R&D) that focuses on key phenome...
Graphite is an important and often life-limiting component for reactors. It is used as a structural ...
Data were developed to compare the extent of structural damage associated with high temperature expo...
Nuclear graphite is proposed for use in High-temperature Gas-cooled Reactor (HTGR) designs as the ne...
An air-ingress accident followed by a pipe break is considered as a critical event for a very high t...
The objective of this project was to perform stress analysis for graphite support structures of the ...
The very high temperature reactor (VHTR) is the latest generation of high-temperature gas-cooled rea...
The Idaho National Laboratory (INL), under the auspices of the U.S. Department of Energy, is perform...
A primary-pipe break accident is one of the design-basis accidents of a high-temperature gas-cooled ...
Air ingress with graphite burning belongs to the accident scenarios in HTRs with potentially severe ...
In this study, the oxidation characteristics of nuclear grade graphites IG-110, IG-430, Type A(MA), ...
Graphite is used in the gas-cooled nuclear reactors as both a neutron moderator and structural compo...
Dissertation supervisor: Dr. Tushar K. Ghosh nad Dr. Sudarshan K. Loyalka.Includes vita.One of the m...
Doctor of PhilosophyDepartment of Mechanical and Nuclear EngineeringHitesh BindraHelium-cooled, grap...
The U.S. Department of Energy is performing research and development that focuses on key phenomena t...
The US Department of Energy is performing research and development (R&D) that focuses on key phenome...
Graphite is an important and often life-limiting component for reactors. It is used as a structural ...
Data were developed to compare the extent of structural damage associated with high temperature expo...
Nuclear graphite is proposed for use in High-temperature Gas-cooled Reactor (HTGR) designs as the ne...
An air-ingress accident followed by a pipe break is considered as a critical event for a very high t...
The objective of this project was to perform stress analysis for graphite support structures of the ...
The very high temperature reactor (VHTR) is the latest generation of high-temperature gas-cooled rea...
The Idaho National Laboratory (INL), under the auspices of the U.S. Department of Energy, is perform...
A primary-pipe break accident is one of the design-basis accidents of a high-temperature gas-cooled ...
Air ingress with graphite burning belongs to the accident scenarios in HTRs with potentially severe ...
In this study, the oxidation characteristics of nuclear grade graphites IG-110, IG-430, Type A(MA), ...