Research Thrust for Reliable Plasma Heating and Current Drive using ICRF
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1 Research Thrust for Reliable Plasma Heating and Current Drive using ICRF J.B.O. Caughman, D.A. Rasmussen, L.A. Berry, R.H. Goulding, D.L. Hillis, P.M. Ryan, and L. Snead (ORNL), R.I. Pinsker (General Atomics), J.C. Hosea and J.R. Wilson (PPPL)
2 Research Thrust for Reliable Plasma Heating and Current Drive using ICRF Research Thrust Summary Address issues needed to ensure reliable ICRF H&CD Integrated modeling effort to understand RF interactions from the antenna to the core Validation of the models using dedicated test stands and facilities 2 Managed by UT-Battelle near-field RF plasma interactions RF breakdown PMI issues existing/upgraded confinement devices. Issues and Gaps with ICRF Antennas Scientific and Technical Requirements to Address the Issues Summary
3 Issues and gaps with ICRF Antennas Plasma heating and current drive using the Ion Cyclotron Range of Frequencies (ICRF) are important elements for the success of fusion Most DEMO concepts identify ICRF as the main heating system Launching structures for ICRH or LHCD must operate in a high radiation, high heat-flux environment The exposed antenna surfaces must be resistive to high heat (1-10 MW/m 2 ) and neutron fluxes with acceptable levels of impurity production DEMO will require operating at ~700 C The issues and gaps cut across the disciplines of plasma theory and simulation, RF technology, materials, diagnostics, and reactor engineering (reliability and maintenance) 3 Managed by UT-Battelle
4 Issues and gaps with ICRF Antennas Many of the issues concern the interaction of the near field of the antenna with the plasma in the scrape of layer (SOL) The RF plasma sheath depends on the antenna structure/phasing The resulting hot spot formation and enhanced local erosion serves as a local impurity source and can degrade core confinement The parasitic RF losses in this region include edge modes, parametric instabilities, and non-linear wave-particle interactions. RF breakdown/arcing is one of the main power limiting issues with operating the antenna in the plasma environment and is poorly understood The anticipated large outer gap on DEMO (and ITER) and the resulting impact on loading will likely push operating voltages to at least as high as the ITER design limit of 45 kv The interactions of the plasma with the antenna surfaces (including ELMs) result in particles and local gas load that affect breakdown and loading The antenna structure and Faraday shield will likely be constructed from layered or coated materials and the behavior of these structures in a nuclear environment is a concern 4 Managed by UT-Battelle
5 Issues with coupling through the SOL Many of the issues concern the interaction of the near field of the antenna with the plasma in the scrape of layer (SOL) The RF plasma sheath depends on the antenna structure/phasing The resulting hot spot formation and enhanced local erosion serves as a local impurity source and can degrade core confinement The parasitic RF losses in this region include edge modes parametric instabilities, and nonlinear wave-particle interactions. C-Mod NSTX 5 Managed by UT-Battelle
6 RF Breakdown and power handling Issues RF breakdown/arcing is one of the main power limiting issues with operating the antenna in the plasma environment and is poorly understood The anticipated large outer gap on DEMO (and ITER) and the resulting impact on loading will likely push operating voltages to at least as high as the ITER design limit of 45 kv The interaction of the plasma with the antenna surfaces (including ELMs) and the role of the resulting particles and local gas load on breakdown and loading 6 Managed by UT-Battelle
7 Uncertainty in plasma density profiles The plasma density profile in the scrape-off region between the separatrix and the antenna determines the loading (how easy it is to couple power to the plasma) It is probably the biggest uncertainty in the ICH system design Can cause factor > 3 uncertainty in power-handling ability Plasma density profiles for 3 antenna-separatrix gaps for ITER Scenario 2 (burning, Q = 10) plasma cm 8 cm 13 cm 13 cm 17 cm 17 cm Density (10 19 m -3 ) Propagation begins for k z 8 m -1 Propagation begins for k z 4 m -1 Density (10 19 m -3 ) Propagation begins for k z 8 m -1 Propagation begins for k z 4 m -1 Short-decay density profile Distance from antenna (cm) 7 Managed by UT-Battelle Long-decay density profile Distance from antenna (cm)
8 Layered materials in a nuclear environment The antenna structure and Faraday shield will likely be constructed from layered or coated materials, and the behavior of these structures in a high temperature nuclear environment is a concern Production of radiation-induced defects (vacancies, interstitials, traps, ) Changes of microstructure including surface Change of chemical composition (transmutation, He production) Degradation of IC material properties: 8 Managed by UT-Battelle ductility (hardening) He embrittlement Thermal conductivity Increased swelling Grain boundary See Theme IV talks by Kurtz, Stoller, etc.
9 ITER- ICRH antenna FS element design Cross section through the bar mm Be CuCrZr /8 SS tubes Stainless steel 30 mm Protection bars Top/bottom Faraday Screen Bars Manufacture : HIP or brazing G. Agarici 12/12/2007 Cadarache Protection bars Left/Right 9 Managed by UT-Battelle
10 Scientific and Technical Requirements to Address the Issues There are fundamental gaps in our understanding of the RF/plasma interface Reliable and predictable antenna operation will not be possible unless these gaps are closed The approach should include: Integration of fully 3-D heating codes with realistic antenna and confinement device geometry is needed to understand the coupling of RF power from the antenna to the core Fundamental understanding of factors that will limit antenna operation, such as ELMs, parasitic losses, and breakdown Nuclear materials issues An integrated effort will need fundamental improvements in modeling coupled with experimental validation of the models on both dedicated test stands and on confinement devices. 10 Managed by UT-Battelle
11 Modeling Effort Requirements The modeling effort requires integration of many existing codes as well as improvement in or construction of new codes Sheath and near field modeling need 3D antenna structures with self-consistent current distribution in the presence of anisotropic magnetized plasma in the scrape off region Models need to be able to couple wave interactions from the antenna surfaces to full wave propagation/absorption in the core plasma The models must also be able to explain why the plasma operation degrades vacuum voltage standoff, including ELM effects Re(E // ) (V/m for feeder), x=5mm 1.5 Upper box corner zone TOPICA Model Lower box corner zone z (m) Material modeling is needed, including the effects of high neutron fluxes, tritium retention, erosion expectations, joining/bonding of materials, and heat transfer at elevated temperatures Modeling components need to be validated on Confinement Experiments and Test Stands (RF and PMI) 11 Managed by UT-Battelle
12 RF Test Stand Validation An RF test stand will allow for the detailed study and understanding of antenna/plasma interactions without impacting valuable confinement machine time until the majority of the model inputs are verified, including: SOL interactions, including RF sheath dynamics, antenna phasing effects, hot spot formation, localized erosion, transport along and across magnetic field lines, and wave-particle interactions Detailed/accurate measurements of plasma density, electron temperature, and potentials in the vicinity of the antenna, together with IR measurements to determine power fluxes Arcing/breakdown issues can also be addressed where multiple parameters can be controlled and tested New diagnostics, control models, and antenna concepts can be developed and operationally verified before implementation on a confinement experiment A dedicated RF test stand will allow for easy access and rapid changes in antenna geometry or test conditions 12 Managed by UT-Battelle
13 RF Test Stand Requirements Plasma volume on the order of a cubic meter at a density of ~10 18 /m 3 with a magnetic field strength of ~1 Tesla Test region large enough to insert a moderate size two-strap variable phase antenna (30 cm wide, 60 cm high) Magnetic connection lengths of ~1 meter, and numerous plasma diagnostics The plasma can be created by a variety of methods, including high-field launched microwaves at 28 GHz (or 53.2 GHz) or by using a helicon-based plasma source Long pulse operation (several minutes) is desirable for testing realistic antenna conditions A secondary plasma source, such as a plasma washer gun, could be located on a flux tube attached to the test antenna and pulsed to simulate ELMs 13 Managed by UT-Battelle
14 PMI Test Stand PMI Test Stand Validate materials models to ensure qualified solutions. Main issues include thermal stresses at the joints subjected to high heat and neutron fluxes cracking due to voids in brazes erosion of coatings, and similar issues Requirements [e.g. as in Hillis talk] High incident heat fluxes (1-10 MW/m2) Ability to handle neutron irradiated materials at elevated temperatures 14 Managed by UT-Battelle
15 Neutron Irradiation Alters Bulk PFC Properties Need to test neutron irradiated and toxic plasma facing and internal components under high heat loads and plasma exposure to prepare for DEMO PMI processes (Erosion, fuel retention and dust formation) Thermo-mechanical properties of PFCs (fatigue, shock resistance) Modification of bulk heat transfer properties Testing of the integrity of coatings, brazes, welds for cooling lines, etc. for internal components Need to perform tests under simultaneous high heat loads ~ 10 MW/m 2 and high surface temperature ~ C 15 Managed by UT-Battelle
16 Scientific and Technical Requirements to Address the Issues on Confinement Experiments Validation on Confinement Experiments Requires significant operational time on confinement experiments Allows study of wave propagation, power absorption, and wave interactions with closed flux surfaces Begin with existing antennas in these machines and do targeted experiments with full set of relevant diagnostics Add new or modified antenna structures DESIGNED to test and validate predictions of plasma-wave interactions, plasma heating/current drive, parasitic losses, large-gap coupling issues, impurity generation, elevated temperature operations, and diagnostic/control strategies. Build new antennas for operation and validation that include all aspects in a fully nuclear environment at elevated temperatures and long pulse lengths 16 Managed by UT-Battelle The neutron damage and tritium retention in layered/coated materials in the antenna structure may cause blistering, swelling, and potential delamination of these materials. The potential for RF breakdown and coolant contamination would be greatly increased and needs to be explored.
17 The ICRF Thrust crosses the Matrix Gaps & Issues by Topic Area RF Antennas (ICRF, LH) Reliable and verified techniques for: Develop/extrapolate/innovate new concepts (SOL work needed for this step) Compatibility with cw high heat computing self-consistent heat and Compatibility in nuclear particle fluxes to high-power, energized Low impurity generation components which interact with and alter Sufficient EM-plasma coupling without arcing RAMI Innovation Physics. Theory & Modeling the edge plasma. improved models of RF wave * Computing all wave processes that can lead to edge losses in SOL * Computing process that contribute to RF Breakdown in the antenna structure Technology Development Qualify structural, shield and coating material with which to construct RF Antennas, including joining/bonding technologies. Modeling and development of new materials Tests of coating techniques and advanced refractory alloys and metal doping Existing/Upgraded/New Test Stands Validate techniques for computing heating performance and self-consistent heat and particle fluxes to high-power, energized RF Antenna, which interact with and alter the edge plasma, including RF breakdown in the antenna structure In-situ tests of material surface dynamic response * Validate edge loss processes in existing devices and determine power flow in the SOL Existing/Upgraded/New Non-DT Confinement Facilities Test nuclear-capable RF Antennas on non-nuclear facilities New DT Confinement Facilities Test RF Antennas in a nuclear environment Validate nuclear capable RF Antennas on CTF Integrated long pulse tests of innovative approaches 17 Managed by UT-Battelle
18 Summary: Needs for ICRF on DEMO to fill the gap Benchmarked predictions of SOL parameters and their impact on loading, RF-edge interactions, and materials Temperature, density, and neutral profiles Perp and parallel heat fluxes to Faraday Shield Verified sheath models Validated power coupling model from antenna to core plasma RF breakdown tolerance with an arc protection and arc/elm discrimination system Load tolerant matching with advanced feedback control Demonstrated methods for large gap coupling (gas puffing, etc.) High temperature gas cooled FS, strap, and structural components qualified for operating in a steady state, fully nuclear environment 18 Managed by UT-Battelle
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