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F. GnesottoFrascati, 19 gennaio 2007 Giornata di presentazione del Progetto ITER all’Industria italiana Ruolo dell’Associazione Euratom-ENEA Prof. F. Gnesotto, Consorzio RFX
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F. GnesottoFrascati, 19 gennaio 2007 L’iniettore di fasci di neutri di ITER Il sistema di alimentazioni elettriche di JT-60 SA
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F. GnesottoFrascati, 19 gennaio 2007 Neutral Beam Heating and Current Drive in ITER
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F. GnesottoFrascati, 19 gennaio 2007 Neutral beam injection: principles Ion source Neutraliser Residual ion Dump (RID) Accelerator Plasma
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F. GnesottoFrascati, 19 gennaio 2007 ITER NBI requirements Neutral beam injection is required since the beginning of ITER operation The NBI system consists of 2 (+1) beams for Auxiliary Heating and Current Drive Beam parameters : P=16.5MW I=40A V=1MV ( to heat the core plasma) t pulse=3600s 1MeV neutrals implies negative ions for efficient neutralisation (60%)
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F. GnesottoFrascati, 19 gennaio 2007 NBI injectors in ITER tangential injection On/off axis injection by tilting the beam axis vertically Plan view Vertical cross section view DNB 2+1 NBI
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F. GnesottoFrascati, 19 gennaio 2007 The NBI sub-systems The NBI system can be separated in 4 subsystems: a) The Injector b) The Power Supply and Voltage Distribution System c) The Control and Data Acquisition System d) The Auxiliary Systems.
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F. GnesottoFrascati, 19 gennaio 2007 The injector 15m 5m 9m
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F. GnesottoFrascati, 19 gennaio 2007 Power balance [MW] with 1MeV D Beam
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F. GnesottoFrascati, 19 gennaio 2007 An example: the Neutralizer 2500 3200 1875 O/ALL 720 H 2 or D 2 inlet Cooling water i/o H - or D - Beam on channel walls4.2 MW (max. 0.5 MW/m 2 ) on leading edges0.4 MW (max. 2.2 MW/m 2 ) Total power4.6 MW Power deposition from ion beam interception: Beam on/off5x10 4 Breakdowns4.5x10 5 Heating cycles during ITER lifetime: Additional power deposition due to electrons (stripping losses in SINGAP): on leading edges2.7 MW (max. 26-30 MW/m 2 )
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F. GnesottoFrascati, 19 gennaio 2007 The Power Supply and Voltage Distribution System The Power Supply (PS) and Voltage Distribution System provides the High Voltage (HV) to the accelerator grids (AGPS) and supplies the ion source (ISPS) and the auxiliary components. The power is transmitted to the ion source and the acceleration grids via a HV transmission line, SF6 insulated for -1MV dc to ground. STEP UP TRANSFORMERS POWER SUPPLY BUILDING TRANSMISSION LINE HV DECK BUSHING \\ 70m
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F. GnesottoFrascati, 19 gennaio 2007 Acceleration Grid Power Supplies MAMuG Configuration ParameterValue Main supply-1000 kV / 59 A Grid 1-800 kV / 7 A Grid 2-600 kV / 6 A Grid 3-400 kV / 3 A Grid 4-200 kV / 3 A Current at ground level 40 A Max. voltage ripple 5 % Response time of the load protection system < 200 s
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F. GnesottoFrascati, 19 gennaio 2007 As most of the issues are strongly coupled, they can be tackled and solved only by testing a full scale NBI at full performance in D and H. A Test Facility to install and operate a NBI before operation in ITER is therefore mandatory in order to provide a reliable system. The test facility will be built in Padova Test Facility
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F. GnesottoFrascati, 19 gennaio 2007 Test Facility for a generic site At present work is in progress to adapt the generic site to Padova site, which has been proposed by EU as the Test Facility site Power supply Maintenance Experiment Auxiliary systems Cooling towers Test Facility for a generic site
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F. GnesottoFrascati, 19 gennaio 2007 Test Facility Auxiliary Systems Cryosystem Forepumping system Top flange platform 60 MW cooling tower Heat rejection system Primary Heat Transfer System HV deck TL2 TL1 HV deck platform Experiment ground level gas 100m The auxiliary systems consist of cryogenic plant cooling plant pumping and gas injection plant
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F. GnesottoFrascati, 19 gennaio 2007 Costi (M€) Convertitori27.0 Installazioni e collaudi5.0 Sorgente del fascio7.0 Neutralizzatore, RID, calorimetro5.1 Vessel e condotto8.0 Bobine di compensazione7.9 Totale EU60.0 Componenti assegnati a EU Costi per 2 iniettori
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F. GnesottoFrascati, 19 gennaio 2007 Projects identified: Engineering Validation and Engineering Design Activities for International Fusion Materials Irradiation Facility (IFMIF-EVEDA and/or facility) to qualify the structural materials needed to license DEMO. International Fusion Energy Research Center (IFERC) including a computer simulation center for fusion science, a center for remote experimentation and a center for international design activities for demonstration reactors A new plasma experimental device (Satellite Tokamak), named JT-60SA, in Naka, Japan. The Broader Approach Agreement
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F. GnesottoFrascati, 19 gennaio 2007 The Broader Approach Agreement Allocation of contributions of the Parties (in percentage) Europe contribution 338 M€ (value 5 May 2005) Japanese contribution46 BY (value 5 May 2005)
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F. GnesottoFrascati, 19 gennaio 2007 The satellite Tokamak: JT-60SA M.Matsukawa, Eng. Feature in the design of JT-60SA, IAEA 06 Outline of the JT-60SA Device
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F. GnesottoFrascati, 19 gennaio 2007 Parties contribution to the JT-60SA construction and operation Approximated data in percentage The POWER SUPPLIES will be provided by EUROPE Consorzio RFX will be responsible of: The quench protection system for the superconducting coils (13 M€) The fast power supply system for the in vessel sector coils (0.8 M€)
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F. GnesottoFrascati, 19 gennaio 2007 The quench protection system for JT-60SA First RFX design activity: Identification of the technical solution vacuum Circuit Breaker (VCB) VCB with mechanical bypass in parallel like in the protection unit developed for ITER semiconductors a solution based on semiconductors (like the dc current breakers in RFX toroidal circuit) should be possible for this voltage and current rating and could be preferable Quench Protection System JA conceptual design
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F. GnesottoFrascati, 19 gennaio 2007 Sector Coil AC filter PWM Inverter 6 coils for toroidal direction Thyristor Converter DCL ~ ~~ The fast power supply for the in vessel sector coil of JT-60SA
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F. GnesottoFrascati, 19 gennaio 2007 The IFMIF Facility
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F. GnesottoFrascati, 19 gennaio 2007 The accelerator The RFQ will be built under responsibility of INFN
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F. GnesottoFrascati, 19 gennaio 2007 The RFQ RFQ (Radiofrequency Quadrupole) Linac The RFQ accelerates the beam of 125mA from 95 keV to 5 MeV A longitudinal length of 12.5m is needed The RF operating frequency is 175 MHz RFQ cold model ( CEA Sacley, IPHI-350MHz ) RFQ cold model ( JAERI, 175MHz-4m module ) The budget for RFQ is 17.3 M€.
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