Assessment of database for interaction of tritium with ITER plasma facing materials

Relevance of d-D interactions on neutron and tritium production in IFMIF-EVEDA accelerator prototype

“…However in the collected data of the literature [12,13] for copper material there are not coefficients for traps, and the temperature range (470-1200 K) does not include the lHvllr-t'VL'DA range (293-373 K). Therefore, in the simuiation the trap effect is not considered and is performed out of the suitable temperature range.…”

Control and Application of Ultrahigh Hydrogen Flux in Materials

“…Therefore, there should be simultaneous processes of hydrogen absorption and desorption in the system with gaseous hydrogen and materials under the equilibrium. The hydrogen concentration in materials under equilibrium as a function of the partial pressure of gaseous hydrogen can be summarized as the hydrogen solubility [19][20][21].…”

Tritium loading in ITER plasma-facing surfaces and its release under accident conditions

“…We know that doping the surface of graphite with B alters the retention characteristics for H isotopes, [7] but there is little if anything known of the effects of W or Be impurities on H retention characteristics of C surfaces. [9] have given sufficient information to estimate with reasonable assurance the inventories to be expected and the release kinetics for tritium in components made from ordinary W. If plasma-sprayed W is used, unless it is formed at very high density, the W will be a porous screen, and except for trapping in the W grains, permeation characteristics will depend on the substrate under the W. is not yet fully known how defects induced by neutron irradiation, especially in a fusion-neutron environment, will affect t r i t i u m retention in any of these materials.…”