Overview of the performance of the JET Active Gas Handling System during and after DTE1

Fuel Cycle Concept of Tokamak Ignitor

“…-измерение количества трития на объекте с использованием комплекса параметров -давления, объёма, температуры, концентрации невозможно, а калориметрические измерения количества трития на месте обладают низкой экспреcсностью, точностью и воспроизводимостью из-за многочасовых временных промежутков, требуемых для охлаждения геттерной ловушки перед адсорбцией водорода или нагревания для его десорбции [7]; -для этих ловушек характерным является замедление процесса откачки водорода из системы вследствие так называемого «эффекта покрытия», вызванного содержанием в газовой смеси инертного газа;…”

Safe handling experience of a tritium storage bed

“…Uranium (U) will be the most technically feasible material from the delivery and recovery points of view (useful equilibrium pressure isotherm, material stability, etc.). For that reason, it has been used in many tritium facilities for fusion technology [4][5][6][7][8]. However, it also has disadvantages from the safety point of view, such as high pyrophoricity with oxygen, high reactivity with nitrogen, fine powdering, etc., and it is a controlled nuclear material in Japan, even if it is depleted.…”

Operation Scenarios and Requirements for Fuel Processing in Future Fusion Reactor Facilities

“…There have been some demonstrations of fusion fuel cycle in the fusion experimental facilities in the past. [3][4][5][6][7] Basically, the design of ITER Tritium Plant 8) is based on the results of the demonstrations, however, practically its operation scenarios will differ from that of the demonstrations in the past because of application of the new components to the tokamak system, such as cryopumps for the primary torus vacuum pumps 9) and NB auxiliary heating systems, pellet injectors for fuelling, 10) etc., and also requirements for plasma operation and safety described in the later sections.…”