Conveners
PSI and PMI experiments
- Brian Wirth (University of Tennessee - Oak Ridge National Laboratory)
PSI and PMI experiments
- Kalle Heinola (IAEA)
Tritium (T) transport through the first wall into the coolant is a major concern in fusion reactor studies. When irradiated by plasmas, hydrogen permeation flux through in-vessel components would be significantly higher than that of gas-exposure cases. To support reactor design studies, low energy plasma-driven hydrogen isotope permeation through the first wall has been extensively...
In future thermonuclear devices such as DEMO displacement damage by 14 MeV fusion neutrons will be created in the plasma-facing materials while they are exposed to high fluxes of ions and neutrals of hydrogen isotopes (HIs) at elevated temperatures. It was shown in several studies in the past twenty years that HI retention and transport will be dominated by trapping at the defects created by...
tbc
Tungsten (W) is considered as a promising plasma-facing material for future fusion reactors. W components will be subjected to an intense flux of 14 MeV neutrons. This will result in creation of radiation defects, production of H and He, and transmutation of W to Rhenium (Re). Radiation defects can trap tritium fuel, posing a stringent limitation to tritium self-sufficiency.
MeV self-ion...
To investigate the effects of particle flux on deuterium (D) retention, a series of D plasma exposures were systematically investigated in recrystallized tungsten (W) at ~500 K using two linear plasma devices STEP and Magnum-PSI. A low flux plasma with the highest fluence of 1.0×10^28 m^-2 was achieved in STEP and a high flux plasma with the highest fluence of 1.0×10^29 m^-2 was achieved in...
