17 th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 1 B. Schunke D. Bora, J.-J. Cordier, R. Hemsworth, A. Tanga V. Antoni & RFX Team T. Bonicelli & EU NB group A. Chakraborty & IN NB group T. Inoue, K. Watanabe & JA NB group Negative Ion based Heating and Diagnostic Neutral Beams for ITER

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 2 of 21 ITER R=6.2 m I p =15 MA P fus =500 MW 30 m 24 m

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 3 of 21 Neutral Beams for ITER

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 4 of 21 Introduction Negative Ion Beams for ITER –The Heating Neutral Beams –The Diagnostic Neutral Beam Neutral Beam R&D Summary and Outlook

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 5 of 21 Mission for H&CD systems for ITER H&CD systems in ITER must provide the tools necessary to achieve the production of thermonuclear power and Q=10 and to demonstrate the feasibility of fusion power; demonstrate sufficient current drive (CD) capability to aim at steady state operation; provide additional “services” such as mode control, machine conditioning and assist in plasma start up and diagnosis; have the flexibility to insure effective and stable burn control. Introduction

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 6 of 21 Operation scenarios Plasma operation has been designed with variable combinations of heating and current drive systems: 2 (3) NB H&CD injectors 33 – 50 MW, 20~40MW ECH, 20~40MW ICH, 0~40MW LH; 3 MW ECH for start up, 3.5 MW DNB. ITER Baseline 2004: Start-up configuration requires 33 MW NB (2), 20MW ICH, 20MW ECH, 0MW LH; 3 MW ECH for start up, 3.5 MW DNB on Day1. The machine configuration is consistent with the possibility of implementation of various operating scenarios. Infrastructure for Heating systems has to be compatible. Introduction

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 7 of 21 Introduction ITER baseline scenarios foresee large (  40%) contribution from NB heating, 3 rd injector needed for scenarios 2-4

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 8 of 21 Power delivered to the plasma per injector HNB (2 + 1) 16.7 MW DNB 3.6MW (excl. duct losses) Beam energy1MeV (D-) / 870keV (H-) 100 keV (H-) Accelerated ion current40 A (D-) / 46 A (H-)60 A (H-) Average accelerated ion current density 200 A/m 2 (D-) / 300 A/m 2 (H-) **** 300 A/m 2 Current density uniformity over the extraction area  10 % Pulse length≤ 3600 s5Hz mod. 1/6 ITER pulse Beamlet divergence< 7 mrad Summary of the design parameters for heating and current drive (H&CD) & Diagnostic NBI system for ITER. **** achieved 280 A/m 2 of H for < 5s Negative Ion Beams for ITER

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 9 of 21 The Injector can be separated in beam components (Ion Source, Accelerator, Neutralizer, Residual Ion Dump and Calorimeter) other components (cryo-pump, vessels, fast shutter, duct, magnetic shielding, and residual magnetic field compensating coils), bushing The HNB injector 15m 5m 9m Negative Ion Beams for ITER (HNB) Weight >250 tons Connected to tokamak via NB duct

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 10 of 21 DNB needed for Charge Exchange Recombination Spectroscopy (CXRS), only possibility to measure He density profiles in a tokamak (He ash); also self consistent code CHEAP CXRS cross sections of atomic transitions => beam energy Good S/N => High current density & beam divergence, beam modulation Negative Ion Beams for ITER (DNB) Beam Bushing PMS Beam vessel Upper correction coils Passive Magn. Shield Same RF ion source, but simplified accelerator But higher current density: material fatigue limitations

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 11 of 21 East West North The NB injectors are installed in the equatorial level of the tokamak building: NB cell NB directly connected to torus vacuum => high dose rate, high activation Remote handling for interventions and maintenance Temporary wall to allow installation of the 3 rd injector HNB#1 HNB#3 HNB#2 DNB Negative Ion Beams for ITER

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 12 of 21 NB Power Supplies Negative Ion Beams for ITER

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 13 of 21 All Heating and Current Drive systems are procured in kind HNB and DNB ( EU & JA, IN ) ICH & CD ( EU, US, IN ) ECH & CD, Start up ( EU, JA, RF, IN ) LHCD (no procurement package) ITER IO provides integration Department for CODAC & IT, Heating and CD, Diagnostics (CHD) – Director D. Bora (presentation Wednesday 9:00) H & CD Division: Head A. Tanga ITER Man PowerS.H. : Senior Technical Officers (3.5 of 5) Phy/Eng : Technical Officers (9) Technical Assistants : (28) R. Hemsworth (NB), B. Schunke (NB), B. Beaumont (ICH &LH), N. Kobayashi (ECH) ITER relies on collaboration with partners, who have chosen to set up ITER in this form Negative Ion Beams for ITER

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 14 of 21 ITER Research & Development Brief H&CD systems must be built and installed in ITER minimizing cost and risk in order to be on schedule and operate efficiently. H&CD systems are critical & essential for fusion research; hence critical technologies need to be developed for ITER and for DEMO. Pursue collaboration of the whole fusion community in the development and research in various areas related to H&CD systems. It is foreseen that following the initial operations, systems will be upgraded during the operational phase of ITER. => applicable to NB systems Neutral Beam R&D

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 15 of 21 Present plan for NB R&D Present plan for NB R&D (Host EU, but JA and IN part.) Establish Neutral Beam Test facility (NBTF) at Consorzio RFX, Padua, Italy (full 1MeV capability) The present plan is to start very early (tendering Jan 2008), the procurement of a full body of one injector and install in Padua for a total time of 10 years. Additionally there will be a second test line devoted to the development of the NB source, common between HNB and DNB, and the testing of DNB (possible in India). Non reusable items and special R&D will be supported by ITER R&D cash fund with a total sum of 8.8 kIUA. Building and services 31MEuros EU+Host Manpower for detail design (EU-JA-IN ) and professionals for operations (EU+PTs TBN) Neutral Beam R&D

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 16 of 21 ITER HNB – Neutral beam test facilty Power supply Maintenance Experiment Auxiliary systems Cooling towers Generic NBTF site layout A full power 1MeV, 40A, D -, 3600 s test bed will be built at RFX, Padua, Italy Neutral Beam R&D

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 17 of 21 Milestones 1. Start tendering Jan Shipping of High Voltage JA PS to test facility Jan Common testing of the HNB & DNB Ion source with complete optimization for DNB Aug 2010 to Test of DNB start 2012 end Start HV tests Feb 2013 end Delivery schedule: Injector-1 will be assembled directly in Cadarache by 2016 with inputs from R & D. Injector-2 in End 2017 from Padua. 7. DNB components are brought to Cadarache Jan Target: First ITER plasma end of 2016 Neutral Beam R&D

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 18 of 21 Additional (and possible future) support (non exclusive): Accelerator testing in 1MeV testbeds in CEA Cadarache, JAEA JA Ion source development MPI, Garching, Germany **** Calorimeter design IN collaborated with NB Juelich, Germany Cryo-pump development, FZK Karlsruhe, Germany Neutralizer Modeling, CNRS, France Negative Ion Source Modeling & Ion Source Diagnostics, Sofia University, Bulgaria Worldwide collaboration Active support from CCNB (Coordinating Committee on Neutral Beams) Create forum for exchange / workshop / meeting to accompany NB R&D Neutral Beam R&D **** Schroedinger Preis der Helmholtzgesellschaft 2006 Adopted as ITER reference ion source, DCR in 2007

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 19 of 21 Additional (and possible future) support (non exclusive): Basic physics studies of beam plasma interaction Alternative ion source development (alternative to caesium ?) Alternative (optical) neutralizer design Material testing Development of neutral beam code Beam plasma interaction physics ITER Tasks, can be given to individual labs or DA, also ITER R&D fund for specific tasks Neutral Beam R&D

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 20 of 21 Summary and Outlook (1) Summary Work in 2007 has concentrated on finalizing Baseline 2007 Procurement arrangement for the NBTF: power supply and sources NB cell design including Integration tasks: –Finalize NB Cell lay-out –Installation sequence studies –Cooling requirements Ongoing Complete documentation and interface documents, e.g. Plant breakdown structure (PBS); System requirements document (SRD) Implementation of the Design Change Requests from design review R & D in specific areas of all H&CD including NBs to meet Day 1 requirements

17th IAEA TM on Research Using Small Fusion Devices, Lisbon B. Schunke 21 of 21 Outlook Neutral Beam design freeze January 2008 so that the detailed design phase can start. Majority of procurement packages to be issued in 2008 NBTF full power testbed for NB issues in Padua, Italy: collaboration of EU, JA, IN Summary and Outlook (2)