Increasing the use of the JET facilities for Fusion Technology R&D in preparation of ITER was one of the key objectives assigned to EFDA in 1999. For this purpose, the JET Fusion Technology Task Force (TF-FT) was set-up in 2000 when JET started being used under EFDA. Over the last five years, 68 Tasks involving several European laboratories have been launched. The programme focuses on tritium, plasma facing components, waste management, engineering and safety issues.

The use of the JET facility is of crucial importance in the testing of technological solutions for ITER. Within the JET Fusion Technology Task Force, several ITER relevant issues have been addressed. Future activities will continue to support ITER designing and licensing activities.

Tritium in the Tokamak & Plasma facing components (EURATOM-Associations UKAEA-UK, TEKES-Finland, FZK-Germany, IPP-Germany, VR-Sweden, CEA-France) In view of limiting the tritium inventory inside ITER, activities are carried out to understand and control the co-deposition of tritium and carbon. The use of JET, with its worldwide unique capability to operate with tritium, is invaluable. Investigations carried out to find how and where tritium is trapped inside JET are based on the analysis of tiles removed during shutdowns (including the use of markers such as 13C) or codeposition monitoring. Methods based on laser or flash lamp are being investigated for removing tritiated codeposited layers from plasma-facing components, with tests carried out in laboratories and a first in-situ demonstration of the flash-lamp inside JET in 2004.

Tritium processes & waste management (EURATOM-Associations SCK-CEN Belgium, FZK-Germany, IPP-Germany, CEA-France, UKAEA-UK, MEC-Romania). Deuterium and tritium from the torus, are processed in the JET Active Gas Handling System (AGHS). A cryopanel prototype has been successfully tested during Trace Tritium Experiments in October 2003 to pump gas from the torus and neutral beam injectors, and could find application on ITER. A new ITER relevant purification system (PERMCAT) has also been tested in AGHS to remove impurities like He, CO2, H2O, CH4 from the collected gases. Following the purification, the different hydrogen species (H, D and T) are sorted out and D and T are stored for JET fuelling.

Dedicated procedures for decreasing the tritium content inside the materials removed from the torus are being developed for tritiated stainless steel, carbon-based materials (graphite and carbon fibre composite), organic liquids (pump oils, liquid scintillation cocktails) together with process and housekeeping wastes.

The design of a fully integrated water detritiation plant as well as the testing of all its key components has been carried out. This work has driven R&D in preparation of the ITER plant and could find application at JET for onsite tritium recovery from tritiated water.

Safety & Engineering and Test beds (EURATOMAssociations ENEA-Italy, SCK-CEN-Belgium, CEAFrance). With 20 years of operation, the use of tritium, beryllium and remote handling for maintenance, the JET experience provides a unique source of information for ITER licensing and guidelines for ITER design. Data are collected on component failure rates in various sub-systems (AGHS, vacuum system, heating systems, power supply) and on occupational radiation exposure (dose to the workers depending on worker categories and operation conditions).

Elements of the JET facilities are also used as test beds for studying prototypes for ITER, such as bypass switches for power supplies, carbon-based tiles under high ion loads or optical fibres under D-T neutron irradiation.