A5075655065- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Fusion materials and technologies
- Electromagnetic Launch and Propulsion Technology
- Physics of Superconductivity and Magnetism
- Particle Accelerators and Free-Electron Lasers
- Plasma Diagnostics and Applications
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Antenna Design and Analysis
- Nuclear reactor physics and engineering
- Particle Detector Development and Performance
- Geophysics and Gravity Measurements
- Gyrotron and Vacuum Electronics Research
- Nuclear Materials and Properties
- Spacecraft and Cryogenic Technologies
- Particle physics theoretical and experimental studies
- Nuclear Physics and Applications
- High-Energy Particle Collisions Research
- Photocathodes and Microchannel Plates
- Engineering Applied Research
- Electromagnetic Compatibility and Measurements
- Calibration and Measurement Techniques
- Superconductivity in MgB2 and Alloys
Massachusetts Institute of Technology
2010-2025
Plasma Technology (United States)
2013-2025
Fusion Academy
2012-2025
Fusion (United States)
2011-2025
Caerus Molecular Diagnostics (United States)
2018
Concordia University
2018
Virginia Commonwealth University
2018
Wuhan University
2018
Beijing University of Chemical Technology
2018
Université Joseph Fourier
2010
Abstract High-temperature superconductors (HTS) promise to revolutionize high-power applications like wind generators, DC power cables, particle accelerators, and fusion energy devices. A practical HTS cable must not degrade under severe mechanical, electrical, thermal conditions; have simple, low-resistance, manufacturable electrical joints; high stability; rapid detection of runaway quench events. We designed experimentally qualified a vacuum pressure impregnated, insulated, partially...
The SPARC Toroidal Field Model Coil (TFMC) Program was a three-year effort between 2018 and 2021 that developed novel Rare Earth Barium Copper Oxide (REBCO) superconductor technologies then successfully utilized these to design, build, test first-in-class, high-field (∼20 T), representative-scale (∼3 m) superconducting toroidal field (TF) coil. program executed jointly by the MIT Plasma Science Fusion Center (PSFC) Commonwealth Systems (CFS) as technology enabler of pathway fusion energy,...
The SPARC Toroidal Field Model Coil (TFMC) is the first large-scale (∼3 m), high-field (∼20 T) superconducting fusion magnet based on Rare Earth Yttrium Barium Copper Oxide (REBCO). Its objective was to retire risk for toroidal field in tokamak, a burning plasma class magnetic confinement energy device. Weighing 10,058 kg and utilizing 270 km of REBCO, TFMC non-insulated, stack-in-plate style magnet. It has three main components: (1) winding pack; (2) structural case; (3) case extensions, or...
The object of this review is to summarize the achievements research on Alcator C-Mod tokamak [Hutchinson et al., Phys. Plasmas 1, 1511 (1994) and Marmar, Fusion Sci. Technol. 51, 261 (2007)] place that in context quest for practical fusion energy. a compact, high-field tokamak, whose unique design operating parameters have produced wealth new important results since it began operation 1993, contributing data extends tests critical physical models into parameter ranges regimes. Using only...
The SPARC Toroidal Field Model Coil (TFMC) experimental tests are described. include detailed comparisons to a hierarchy of electromagnetic and structural models the coil. confirmed ability no-insulation no-twist (NINT) configuration provide highly stable DC operations with peak magnetic field in excess 20 tesla at REBCO tape stacks. advantages modular TFMC approach were validated including test probe response coil stages; strategy that will be applied large-scale production for SPARC....
A new superconducting magnet test facility was created at the MIT Plasma Science and Fusion Center (PSFC) for SPARC Toroidal Field Model Coil (TFMC) program. The designed constructed in parallel with TFMC between 2019 2021, capabilities design approaches tailored to needs of this project its timeline. major components include a cryostat (outer dimensions, 5.3 m×3.7 m×1.5 m) open bore; novel cooling system circulating supercritical helium closed-loop provide ∼600 W power ∼20 bar-a, K; 50 kA,...
This paper presents design, fabrication, and operational results for a novel pair of binary Current Leads (CLs). The CLs were purpose built the SPARC Toroidal Field Model Coil (TFMC) Test Facility at MIT Plasma Science Fusion Center. approximately 3 m tall demonstrate stable operation current ramp rates up to 50 kA/s steady-state currents kA from ambient temperature power supplies facility's 20 K test environment. Each CL can be divided into three main parts: an upper copper heat exchanger...
The MIT Plasma Science and Fusion Center collaborators are proposing a high-performance Advanced Divertor RF tokamak eXperiment (ADX)-a specifically designed to address critical gaps in the world fusion research programme on pathway next-step devices: nuclear science facility (FNSF), pilot plant (FPP) and/or demonstration power (DEMO). This high-field (>= 6.5 T, 1.5 MA), high density (P/S similar MW m(-2)) will test innovative divertor ideas, including an 'X-point target divertor' concept,...
Abstract Fiber-optic thermometry has the potential to provide rapid and reliable quench detection for emerging large-scale, high-field superconducting magnets fabricated with high-temperature-superconductor (HTS) cables. Developing non-voltage-based schemes, such as fiber Bragg grating (FBG) technology, are particularly important applications magnetic fusion devices where a high degree of induced electromagnetic noise impose significant challenges on traditional voltage-based methods. To...
This paper reviews the physics and technology of wave-particle-interaction experiments in ion cyclotron range frequencies (ICRF) lower hybrid (LH) (LHRF) on Alcator C-Mod tokamak. Operation fixed frequency (80 MHz) tunable (40- to 80-MHz) ICRF transmitters associated transmission system is described. Key fabrication issues that were solved order operate a four-strap antenna compact environment are discussed some detail. heating utilizing hydrogen (H) helium-3 (3He) minority schemes...
Abstract The benefits of operating fusion devices, such as tokamaks and stellarators, at high fields make high-temperature superconducting magnets necessary to realize a compact power system. Superconducting W7-X, have used standard low-temperature superconductor technology niobium-titanium. ARPA-E has recently funded two-year project led by the startup Type One Energy involving Fusion Technology Institute University Wisconsin-Madison, Plasma Science design fabricate first non-planar (HTS)...
Abstract A low-AC loss Rare-earth barium copper oxide (REBCO) cable, based on the VIPER cable technology has been developed by commonwealth fusion systems for use in high-field, compact tokamaks. The new is composed of partitioned and transposed ‘petals’ shaped to fit together a circular pattern with each petal containing REBCO tape stack insulated from other reduce AC losses. stainless-steel jacket adds mechanical robustness—also serving as vessel solder impregnation—while tube runs through...
The world's largest pulsed superconducting coil was successfully tested by charging up to 13 T and 46 kA with a stored energy of 640 MJ. ITER central solenoid (CS) model CS insert were developed fabricated through an international collaboration, their cooldown tests carried out test operation teams. In tests, where the original goal 0.4 T/s T, achieved ramp rates 0.6 1.2 T/s, respectively. addition, charged discharged 10 003 times in background field no degradation operational temperature...
A one dimensional, absolutely calibrated pinhole camera system was installed on the DIII-D tokamak to measure edge Lyman-alpha (Ly-α) emission from hydrogen isotopes, which can be used infer neutral density and ionization rate profiles. The is composed of two cameras, each providing a toroidal fan 20 lines sight, viewing plasma inboard outboard side DIII-D. cameras’ views lie in horizontal plane 77 cm below midplane. At its tangency radius, channel provides radial resolution ∼2 full width at...
From June 2019 to July 2021, the MIT Plasma Science and Fusion Center in collaboration with Commonwealth Fusions Systems (CFS) designed, built, commissioned a test facility at evaluate performance of REBCO-based, 2.9-m tall, 1.9-m wide Toroidal Field Model Coil (TFMC) for SPARC tokamak. This paper presents facility's supercritical helium (SHe) circulation system design measured performance. The employed forced-flow SHe-circulation loop cooled by cryocoolers provide nominal cooling power 600...
The design, construction and initial results of a new lower hybrid current drive (LHCD) launcher on Alcator C-Mod (Hutchinson et al 1994 Phys. Plasmas 1 1511) are presented. LHCD (LH2) is based novel splitter concept which evenly distributes the microwave power in four ways poloidal direction. This design allows for simplification feeding structure while keeping flexibility to vary peak launched toroidal index refraction, Ntoroidal, from −3.8 3.8. An integrated model predicts good plasma...
This paper summarizes highlights of research results from the Alcator C-Mod tokamak covering period 2006–2008. Active flow drive, using mode converted ion cyclotron waves, has been observed for first time in a plasma, mix D and 3 He species; toroidal poloidal flows are driven near location conversion layer. ICRF induced edge sheaths implicated both erosion thin boron coatings generation metallic impurities. Lower hybrid range frequencies (LHRF) microwaves have used efficient current profile...
Abstract We present the design and first results of an assembly that enables rare earth barium copper oxide (REBCO) superconducting cables—the VIPER cable in this work—to be tested SULTAN facility under simultaneous application transverse electromechanical loading axial mechanical strain. The objective is to emulate loads a REBCO would experience three-dimensional coil but shorter simpler straight cables, reducing cost, schedule, complexity high-fidelity conductor qualification. uses two...
A correlation electron cyclotron emission (CECE) diagnostic has been installed in Alcator C-Mod. In order to measure temperature fluctuations, this uses a spectral decorrelation technique. Constraints obtained with nonlinear gyrokinetic simulations guided the design of optical system and receiver. The CECE is designed fluctuations which have k(θ) ≤ 4.8 cm(-1) (k(θ)ρ(s) < 0.5) using well-focused beam pattern. Because dedicated turbulence diagnostic, also flexible, allows for various...
We describe some of the engineering solutions required to produce a diverted tokamak capable operation with toroidal field 8 T and plasma currents up 2 MA. Some design details magnet, ohmic heating metal plasma-facing components, rf current drive systems, power liquid nitrogen cooling systems are discussed. Vacuum, vessel bake, boronization, wall-cleaning also Finally, disruption research results from Alcator C-Mod presented.
Recent research on the Alcator C-Mod tokamak has focused a range of scientific issues with particular emphasis ITER needs and detailed comparisons between experimental measurements predictive models. Research ICRF (ion cyclotron frequencies) heating emphasized origins mitigation metallic impurities while work lower hybrid current drive experiments have linear nonlinear wave interactions that limit efficiency at high densities in regimes low single pass absorption. Experiments core turbulence...