Abstract
Graphite is extensively being used in present‐day fusion devices and has been selected as the reference material for plasma‐facing components in the international thermonuclear experimental reactor, ITER. Graphite’s major advantages are associated with its low Z and excellent thermomechanical properties. Its drawbacks include susceptibility to erosion and large capacity for H retention under hydrogen plasma exposure. H‐retention affects fuel recycling and also presents a potential environmental risk when operating with tritium, during vacuum vessel maintenance and accidental vacuum loss. The objective of the present study was to investigate the removal of energetically implanted deuterium from pyrolytic graphite via chemical reaction with atmospheric gases (N2, O2, and H2O) for different graphite temperatures. N2 exposure at 300–570 K appeared to be ineffective for the removal of implanted D. Oxygen exposure, on the other hand, was most effective in removing the implanted D from graphite, most likely by t...
Published Version
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a call