Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione

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056 progress report 2010 chapter 3 technologyprogramme The technology program performed by the Association in 2010 cover the most crucial activities related to ITER, the European Fusion Development Agreement (EFDA) program and Broader Approach (BA) agreement. Many of these activities were performed within Consortia established among Association and collaboration with industry. The most relevant results achieved in the period are the following. The ENEA technology developed for the construction of the divertor monoblock plasma facing units has been successfully applied, in collaboration with Ansaldo Nucleare, for the construction of the qualification prototype. An important irradiation experiment has been carried out to assess the design of the ITER shielding blanket. A mock up of the shielding blanket plus vacuum vessel and the toroidal field (TF) magnet (utilizing actual cable–in–conduit (CIC) conductor) has been irradiated. The test results were very useful to reduce the uncertainties on the heat deposited on the superconductors and to better define the shield block design. A number of MCNP models have been developed in the frame of the design of the high resolution spectrometer, the radial neutron camera and the in vessel and divertor coils. Concerning sensor development, further to the continuation of the diamond sensors, gas electron multiplier (GEM) were utilised as neutron detectors. The in vessel viewing system (IVVS) developed by ENEA for ITER has been further improved by adding a vibration filtering system. Safety studies have been performed for studying the mobilization of dusts in the event of a loss of vacuum accident. Experimental and modelling activities were accomplished with also with the aim to develop the proper diagnostic system. In the field of materials, a multi-scale method for modelling ceramic composites has been implemented developing a special subroutine to be utilised in ABAQUS code. In Brasimone the breeder blanket test facilities were further improved with the commissioning of TRItium EXtraction (TRIEX) loop for the simulation of the lithium lead purification system. The Broader Approach activities were mainly focussed on the International Fusion Materials Irradiation Facility (IFMIF) and materials. Target design based on an alternative remote handling scheme has been further developed and the preparation of the experimental activity in EVEDA lithium test experiment (ELITE) facility in Japan has been started. Test facility to investigate the compatibility issues of SiC/SiC in high temperature flowing lithium has been realised. In this frame the construction of lithium purification loop has been completed. As for the Japan Tokamak 60 Super Advanced (JT60–SA), the technical specification of the TF magnet have been finalised and those for the power supply and switching system are in progress. Training activities have been performed in the field of liquid metal, magnet and divertor technology in the frame of the Euratom training scheme.
technology programme (cont’d.) progress report 2010 057 3.1 Divertor, First Wall, Vacuum Vessel and Shield Manufacturing technology for the ITER inner vertical target ENEA has been deeply involved in the ITER R&D activities for the manufacturing of high heat flux plasma–facing components, and in particular for the inner vertical target (IVT) of the ITER divertor. This component has to be manufactured by using both armour and structural materials whose properties are defined by ITER. Their physical properties prevent standard joining techniques from being applied. The reference armour materials are tungsten and carbon/carbon fibre composite (CFC), and, for the cooling pipe, a copper alloy (CuCrZr). During the last years ENEA, in collaboration with Ansaldo, has been manufacturing several actively cooled mock–ups and prototypical components of different length, geometry and materials, by using innovative processes: hot radial pressing (HRP) and pre–brazed casting (PBC). The optimization of the processes started from the successful manufacturing of both W and CFC small scale mockups and successful testing in the worst ITER operating condition (20 MW/m 2 ) through the achievement of record performances obtained from a medium scale IVT CFC and W armoured mockup: after ITER relevant heat flux fatigue testing (20 MW/m 2 for 2000 cycles CFC part, 15 MW/m 2 for 2000 cycles W part) it reached a critical heat flux of 35 MW/m 2 at ITER relevant thermal–hydraulic conditions. On the basis of these results, ENEA–ANSALDO participated in the European program for the qualification and manufacturing of the divertor IVT, according to the Fusion For Energy (F4E) specifications. A divertor IVT prototype (400 mm total length) with three plasma facing component units (fig 3.1) was successfully tested at ITER relevant thermal heat fluxes (20 MW/m 2 for 3000 cycles CFC part, 15 MW/m 2 for 3000 cycles W part). Now, this technology is ready to face the challenge of the ITER IVT production, thus transferring the experience gained in the development, optimization and qualification of the PBC and HRP processes to an industrial production line. Qualification of ultrasonic non–destructrive testing method for plasma facing components Under the “EURATOM Training Network for Plasma–facing Materials” (ETN_PFM) (Contract No. 042314 (FU 06)), ENEA was assigned with a trainee to be prepared in the area of “Design, manufacturing and acceptance procedures of PFC”. This area is strictly linked to the activities related to the Figure 3.1 – ITER divertor IVT qualification prototype manufactured by ENEA–Ansaldo
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