Since the installation of an ITER-like wall, the JET programme has focused on the consolidation of ITER design choices and the preparation for ITER operation, with a specific emphasis given to the bulk tungsten melt experiment, which has been crucial for the final decision on the material choice for the day-one tungsten divertor in ITER. Integrated scenarios have been progressed with the re-establishment of long-pulse, high-confinement H-modes by optimizing the magnetic configuration and the use of ICRH to avoid tungsten impurity accumulation. Stationary discharges with detached divertor conditions and small edge localized modes have been demonstrated by nitrogen seeding. The differences in confinement and pedestal behaviour before and after the ITER-like wall installation have been better characterized towards the development of high fusion yield scenarios in DT. Post-mortem analyses of the plasma-facing components have confirmed the previously reported low fuel retention obtained by gas balance and shown that the pattern of deposition within the divertor has changed significantly with respect to the JET carbon wall campaigns due to the absence of thermally activated chemical erosion of beryllium in contrast to carbon. Transport to remote areas is almost absent and two orders of magnitude less material is found in the divertor.
Within the Tritium Plant of ITER a total inventory of about 2 to 3 kg will be necessary to operate the machine in the DT phase at a throughput of about 1 kg tritium per hour. During plasma operation, tritium will be distributed in the different subsystems of the fuel cycle. A tool for tritium inventory evaluation the dynamic model (TRIMO) of the tritium content in each subsystem of the Fuel Cycle of ITER was developed. The code reflects the design of each system; both the physical processes characteristics of each system and the associated control systems are modeled in TRIMO. The confinement of tritium within the respective systems of the Fuel Cycle is one of the most important safety objectives. The design of the deuterium / tritium fuel cycle of ITER includes a multiple barrier concept for the confinement of tritium and has two major features, namely a two (primary and secondary) barrier design and secondary containment atmosphere and gaseous waste treatment systems. Ultimately the building is equipped with a vent detritiation system and re-circulation type room atmosphere detritation systems, required as an emergency tritium confinement barrier during possible accidental events. In order to assure a high integrity of the tritium bearing systems within the ITER Tritium Plant the design considers largely protection measures (mainly overpressure and overtemperature protection).
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