Tungsten is a candidate plasma facing material under investigation in a San
dia National Laboratories project conducted at Los Alamos National Laborato
ry. Samples of 99.95% tungsten provided by Plansee Aktiengesellschaft were
exposed to 100 eV deuterium and tritium ions at a range of fluxes from 2.3
x 10(17) to 1.3 x 10(18) ions/cm(2) s for one hour at 623 K in the tritium
plasma experiment. The samples were outgassed to determine the amount of re
tained hydrogen isotopes. The retention scaled at slightly greater than the
square root of the fluence. The fractional retention was on the order of 1
0(-5). The data from these experiments were combined with previous results
to construct a comprehensive model of the migration and retention behavior
for hydrogen in tungsten, A second set of experiments involved exposing 99.
95% tungsten foils provided by AESAR to 100 eV deuterons at a flux of 6 x 1
0(17) D/cm(2) s for 30 min at 423 and 373 K, Scanning Electron Microscopy a
nalysis was performed on the samples to determine the effects of the plasma
exposure, Unannealed samples revealed extensive blistering with many blist
er caps removed. Samples annealed to 1473 K showed minor blistering, and sa
mples annealed to 1273 K showed no blistering, The SEM analysis was used in
conjunction with the retention results to understand the role of annealing
and defects in trapping within the tungsten. (C) 2001 Published by Elsevie
r Science B.V.