Detriation studies are critical for assessing the feasibility and cost
s of the ITER disposal plan for tritiated waste. A flexible apparatus
has been commissioned for studying the detritiation of hard waste samp
les, by heating, melting, or dissolving them in molten metal. It is in
stalled in a new laboratory approved for the simultaneous handling of
tritium and beryllium. R.F. heating means the specimen temperature is
limited only by the crucible material. A filter confines beryllium con
tamination to the silica glass specimen tube. There is independent con
trol of carrier gas flow rate and pressure at any value between 10(-7)
mbar and 1 bar. All tubing is warmed to allow the use of wet carrier
gases, and to reduce tritium memory. No organic materials are used. A
specially constructed low-memory bakable ionization chamber and all-gl
ass bubbler-set enable sensitive measurements of the tritium outgassin
g with minimised memory effects.