The TRIO experiment is a test of in-situ tritium recovery and heat transfer performance of a miniaturized solid breeder blanket assembly. The assembly (capsule) was monitored for temperature and neutron flux profiles during irradiation and a sweep gas flowed through the capsule to an analytical train wherein the amounts of tritium in its various chemical forms were determined. The capsule was designed to operate at different temperatures and sweep gas conditions. At the end of the experiment the amount of tritium retained in the solid was at a concentration of less than 0.1 wppM. More than 99.9% of tritium generated during the experiment was successfully recovered. The results of the experiment showed that the tritium inventories at the beg...
The accurate measurement of behavior of bred tritium released from a tritium breeder is indispensabl...
The Tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory is a facility designed to...
In most current designs of D-T fusion reactor blankets employing ceramic breeder materials, the use ...
Tritium and deuterium are expected to be the fuel for the first fusion power reactors. Being radioac...
The tritium recovery experiment, TRIO-01, required a gas analysis system which detected the form of ...
An experiment has been performed to measure the effect of temperature on the outgassing rate of trit...
A reference design study for a Mirror Fusion Hybrid Reactor has been completed which examines the tr...
Development of tritium handling techniques is of great importance for thermonuclear fusion experimen...
Accurate measurement of the nuclear environment within a test tritium breeding-blanket module of a f...
The technical feasibility of a room temperature recombiner (RTR) for detritiation system was demonst...
In a large fusion test facility, when a deuterium-plasma experiment is conducted a small amount of t...
Reliable techniques for storage, supply and recovery of tritium gas are indispensable to ensure safe...
Sandia National Laboratories in California initiated an experimental program to determine whether tr...
Tritium extraction from materials is most commonly carried out using oxidative thermal desorption in...
Experiments have been carried out to understand how tritium, a radioactive isotope of hydrogen, deso...
The accurate measurement of behavior of bred tritium released from a tritium breeder is indispensabl...
The Tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory is a facility designed to...
In most current designs of D-T fusion reactor blankets employing ceramic breeder materials, the use ...
Tritium and deuterium are expected to be the fuel for the first fusion power reactors. Being radioac...
The tritium recovery experiment, TRIO-01, required a gas analysis system which detected the form of ...
An experiment has been performed to measure the effect of temperature on the outgassing rate of trit...
A reference design study for a Mirror Fusion Hybrid Reactor has been completed which examines the tr...
Development of tritium handling techniques is of great importance for thermonuclear fusion experimen...
Accurate measurement of the nuclear environment within a test tritium breeding-blanket module of a f...
The technical feasibility of a room temperature recombiner (RTR) for detritiation system was demonst...
In a large fusion test facility, when a deuterium-plasma experiment is conducted a small amount of t...
Reliable techniques for storage, supply and recovery of tritium gas are indispensable to ensure safe...
Sandia National Laboratories in California initiated an experimental program to determine whether tr...
Tritium extraction from materials is most commonly carried out using oxidative thermal desorption in...
Experiments have been carried out to understand how tritium, a radioactive isotope of hydrogen, deso...
The accurate measurement of behavior of bred tritium released from a tritium breeder is indispensabl...
The Tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory is a facility designed to...
In most current designs of D-T fusion reactor blankets employing ceramic breeder materials, the use ...