The Joint European Torus (JET) carried out the first preliminary exper
iment with a deuterium-tritium plasma in 1991. This utilised an on-sit
e inventory of 0.25g. The future experimental programme for the JET ma
chine includes two discrete phases using plasmas fuelled by deuterium
and tritium. The first of these, in mid-1996, will generate around 2 x
10(20) neutrons and require a site inventory of a few grams of tritiu
m. The second is proposed to take place in 1999 if an extension to the
JET project from 1996 is granted. This will require a few tens of gra
ms of tritium and will generate up to 5 x 10(21) neutrons. The JET Act
ive Gas Handling System has been constructed to enable tritium to be r
ecovered from the plasma exhaust and stored for re-injection. The desi
gn also minimises tritium discharges to the environment. It is current
ly being commissioned to meet the above programme and has been modifie
d to take into account a new requirement for operation over extended p
eriods during maintenance and D-D operation with tritium contaminated
plasma exhaust. Commissioning of the Active Gas Handling System consis
ts of inactive, trace tritium (similar to 40TBq) and full tritium (<3g
) phases. The experience and main results of inactive commissioning ar
e presented and the status of tritium commissioning is reviewed.