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Giornata di presentazione del Progetto ITER all’Industria italiana

Giornata di presentazione del Progetto ITER all’Industria italiana Ruolo dell’Associazione Euratom-ENEA Prof. F. Gnesotto, Consorzio RFX. L’iniettore di fasci di neutri di ITER Il sistema di alimentazioni elettriche di JT-60 SA. Neutral Beam Heating and Current Drive in ITER.

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Giornata di presentazione del Progetto ITER all’Industria italiana

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  1. Giornata di presentazione del Progetto ITER all’Industria italiana Ruolo dell’Associazione Euratom-ENEA Prof. F. Gnesotto, Consorzio RFX Frascati, 19 gennaio 2007

  2. L’iniettore di fasci di neutri di ITER Il sistema di alimentazioni elettriche di JT-60 SA Frascati, 19 gennaio 2007

  3. Neutral Beam Heating and Current Drive in ITER Frascati, 19 gennaio 2007

  4. Neutral beam injection: principles Residual ion Dump (RID) Accelerator Ion source Neutraliser Plasma Frascati, 19 gennaio 2007

  5. 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 P=16.5MW I=40A V=1MV ( to heat the core plasma) t pulse=3600s Beamparameters: 1MeV neutrals implies negative ions for efficient neutralisation (60%) Frascati, 19 gennaio 2007

  6. NBI injectors in ITER 2+1 NBI tangential injection DNB Vertical cross section view Plan view On/off axis injection by tilting the beam axis vertically Frascati, 19 gennaio 2007

  7. The NBI sub-systems The NBI system can be separated in 4 subsystems: a) The Injector b) The Power Supply and VoltageDistribution System c) The Control and Data Acquisition System d) The Auxiliary Systems. Frascati, 19 gennaio 2007

  8. The injector 9m 5m 15m Frascati, 19 gennaio 2007

  9. POWER POWER BEAM BEAM BEAM LINE BEAM LINE 55 55 ¸ ¸ 59 59 SUPPLY SUPPLY SOURCE SOURCE 40 40 ¸ ¸ 17 16 20 20 0.05 0.05 INPUT INPUT to to PLASMA PLASMA POWER POWER 17 17 ¸ ¸ 18 18 2 2 ¸ ¸ 4 5 1 1 4 4 ¸ ¸ 8 8 5 5 0.2 0.6 5 CALORIMETER TRANSMISSION DUCT LINE LINE ION SOURCE NEUTRALISER POWER OTHER COMPONENTS SUPPLY SUPPLY ACCELERATOR RID Power balance [MW] with 1MeV D Beam Frascati, 19 gennaio 2007

  10. 720 3200 H- or D- Beam Power deposition from ion beam interception: • on channel walls 4.2 MW (max. 0.5 MW/m2) • on leading edges 0.4 MW (max. 2.2 MW/m2) • Total power4.6 MW 2500 H2 or D2 inlet 1875 O/ALL Cooling water i/o Heating cycles during ITER lifetime: • Beam on/off 5x104 • Breakdowns 4.5x105 An example: the Neutralizer • Additional power deposition due to electrons (stripping losses in SINGAP): • on leading edges2.7 MW (max. 26-30 MW/m2) Frascati, 19 gennaio 2007

  11. 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. TRANSMISSION LINE HV DECK BUSHING \\ 70m POWER SUPPLY BUILDING STEP UP TRANSFORMERS Frascati, 19 gennaio 2007

  12. Acceleration Grid Power Supplies Frascati, 19 gennaio 2007

  13. Test Facility • 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 Frascati, 19 gennaio 2007

  14. Test Facility for a generic site Test Facility for a generic site Experiment Maintenance Power supply Cooling towers Auxiliary systems 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 Frascati, 19 gennaio 2007

  15. Test Facility Auxiliary Systems cryogenic plant cooling plant The auxiliary systems consist of pumping and gas injection plant TL1 HV deck HV deck platform TL2 Top flange platform gas Forepumping system Heat rejection system Experiment ground level Primary Heat Transfer System 60 MW cooling tower Cryosystem 100m Frascati, 19 gennaio 2007

  16. Costi (M€) Componenti assegnati a EU Costi per 2 iniettori Frascati, 19 gennaio 2007

  17. The Broader Approach Agreement • 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. Frascati, 19 gennaio 2007

  18. The Broader Approach Agreement Allocation of contributions of the Parties (in percentage) Europe contribution 338 M€ (value 5 May 2005) Japanese contribution 46 BY (value 5 May 2005) Frascati, 19 gennaio 2007

  19. The satellite Tokamak: JT-60SA Outline of the JT-60SA Device M.Matsukawa, Eng. Feature in the design of JT-60SA, IAEA 06 Frascati, 19 gennaio 2007

  20. 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 systemfor the superconducting coils (13 M€) • The fast power supply system for the in vessel sector coils (0.8 M€) Frascati, 19 gennaio 2007

  21. S CH - MS C + VCB R Fuse D Dump resistance Pyro-Fuse MCB Backup circuit Coil current The quench protection system for JT-60SA Quench Protection System JA conceptual design • 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 Frascati, 19 gennaio 2007

  22. The fast power supply for the in vessel sector coil of JT-60SA Sector Coil Thyristor Converter AC filter DCL 6 coils for toroidal direction ～ ～ ～ PWM Inverter Frascati, 19 gennaio 2007

  23. The IFMIF Facility Frascati, 19 gennaio 2007

  24. The accelerator The RFQ will be built under responsibility of INFN Frascati, 19 gennaio 2007

  25. 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 The budget for RFQ is 17.3 M€. Frascati, 19 gennaio 2007

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