ABSTRACT: A tritium production method using a high-temperature gas-cooled reactor loaded with lithium compound particles has been proposed for steadily starting up and stably operating a fusion reactor. In order to confine the produced tritium, small lithium-compound particles are considered to be coated by ceramic materials. The present authors have proposed adding zirconium fine particles into the inside of the ceramic coating to improve tritium confinement performance. In this work, powdered zirconium was exposed to hydrogen or deuterium gas in a closed volume at elevated temperatures and absorption rate constant and Sieverts' constant were evaluated by the pressure drop by absorption. After the experiments, it was found that the powdere...
Tritium diffusion measurements have been conducted in Al/sub 2/O/sub 3/, BeO, Y/sub 2/O/sub 3/, SiC,...
We designed an experimental system capable of handling at least 100 Ci tritium in an experimental ru...
In most current designs of D-T fusion reactor blankets employing ceramic breeder materials, the use ...
AbstractUnder tritium production method using a high-temperature gas-cooled reactor loaded Li compou...
Under tritium production method using a high-temperature gas-cooled reactor loaded Li compound, Li c...
Hydriding studies of zirconium on an engineering scale was continued for application to tritium stor...
Development of tritium handling techniques is of great importance for thermonuclear fusion experimen...
For this study, hydrogen getter materials (Zircaloy-4 and pure zirconium) that have a high affinity ...
Reliable techniques for storage, supply and recovery of tritium gas are indispensable to ensure safe...
Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prio...
Zirconium-alloys such as ZrNi and ZrCo have been developed so far as promising materials for storage...
Supply and recovery techniques of tritium gas (T2) on a laboratory scale is important for experiment...
Engineering-scale operation was started on hydriding of zirconium for application to tritium storage...
Under the development of International Thermonuclear Experimental Reactor (ITER) system aimed at rea...
Ongoing experimental studies at ANL aimed at the development of methods to reduce tritium migration ...
Tritium diffusion measurements have been conducted in Al/sub 2/O/sub 3/, BeO, Y/sub 2/O/sub 3/, SiC,...
We designed an experimental system capable of handling at least 100 Ci tritium in an experimental ru...
In most current designs of D-T fusion reactor blankets employing ceramic breeder materials, the use ...
AbstractUnder tritium production method using a high-temperature gas-cooled reactor loaded Li compou...
Under tritium production method using a high-temperature gas-cooled reactor loaded Li compound, Li c...
Hydriding studies of zirconium on an engineering scale was continued for application to tritium stor...
Development of tritium handling techniques is of great importance for thermonuclear fusion experimen...
For this study, hydrogen getter materials (Zircaloy-4 and pure zirconium) that have a high affinity ...
Reliable techniques for storage, supply and recovery of tritium gas are indispensable to ensure safe...
Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prio...
Zirconium-alloys such as ZrNi and ZrCo have been developed so far as promising materials for storage...
Supply and recovery techniques of tritium gas (T2) on a laboratory scale is important for experiment...
Engineering-scale operation was started on hydriding of zirconium for application to tritium storage...
Under the development of International Thermonuclear Experimental Reactor (ITER) system aimed at rea...
Ongoing experimental studies at ANL aimed at the development of methods to reduce tritium migration ...
Tritium diffusion measurements have been conducted in Al/sub 2/O/sub 3/, BeO, Y/sub 2/O/sub 3/, SiC,...
We designed an experimental system capable of handling at least 100 Ci tritium in an experimental ru...
In most current designs of D-T fusion reactor blankets employing ceramic breeder materials, the use ...