THE NEXT LEVEL IN
A massive transition is underway as major populations in emerging economies access modern infrastructure. This is a time of great challenge and opportunity as unprecedented demand is placed on healthcare, education, water, food, transportation and energy. At their foundation is power, and we need to transform how we produce it in order to protect the planet while advancing a more abundant and equitable future for all.
Fusion energy is the clean power at the center of stars. Mastered here on earth, its unique advantages will rapidly disrupt carbon-based fuels to become the primary form of baseload power on the planet.
The stellarator is a fusion power system that uses magnetic fields to confine ionized gas to fusion conditions using fuel obtained from water. Its inherently practical features make it highly attractive to utilities for 24/7 baseload operation that can be deployed almost anywhere. Under development by various nations, the stellarator has been making tremendous strides in recent years towards the goal of generating surplus power, the Kittyhawk moment for fusion.
Type One Energy is founded by experts and technology from the University of Wisconsin, a world leader in stellarator R&D, with the mission to provide clean, affordable fusion power to every city across the globe. In collaboration with its public and private partners, Type One bridges lab-to-market by uniting the outstanding operation of the stellarator with breakthroughs in theory, additive manufacturing, and high temperature superconducting magnets for an economical fusion power plant deployed worldwide in the shortest amount of time.
TRANSFORM THE ENERGY LANDSCAPE
FUEL FROM WATER
Deuterium (H2 or D), a natural hydrogen isotope contained in water, is fused to produce tremendous energy that is four million times more powerful than chemical reactions, such as burning fossil fuels, and four times more than nuclear fission. Costing less than $1 per gram, deuterium is extracted using a simple, established, and environmentally benign industrial process. With only half a gram needed to power an average home for a year, deuterium fuel amounts to much less than one percent the cost of electricity with enough in seawater alone to power the globe for millions of years.
NO HARMFUL IMPACT
The deuterium fuel used in a fusion power system produces inert helium, which is a valuable commodity. No emissions contributing to climate change or pollution are created. There is no carbon footprint from mining, refining, or major transport, as is common with other forms of fuel. The extraction of deuterium has no effect on the water and is restored to the source.
NO MELTDOWNS OR RADIOACTIVE FUEL WASTE
No mechanism for a runaway reaction exists, and any form of meltdown is physically impossible. In the event of an operational failure, the fusion process instantly ceases. There is no fissile material or spent radioactive fuel to store. Neutron activated materials produced by fusion are recycled and cleared for commercial reuse.
SECURE & STEADY
An unvarying and continuous supply of electricity is generated 24/7 by a stellarator power plant. Since the fuel is ubiquitous, near limitless, and very low cost, resource constraints arising from geopolitics, supply issues, and commodity prices, become a thing of the past.
Hydrogen is cleanly produced from the deuterium extraction process and is perfectly suited as an energy storage medium for instant load following using existing industrial-scale equipment.
Fusion power systems can be sized to support localized grids with siting suitable for urban areas right where the energy is used, avoiding the costs of long distance transmission.
CLEAN BASELOAD POWER
FOR MODERN NATION BUILDING
The stellarator is a innovative marriage of elegant physics, engineering artistry, and practical utility.
Invented in the United States by Dr. Lyman Spitzer in 1951, the stellarator uses shaped magnetics to confine extremely hot charged gas along a twisting circular path. The complex magnetic fields are designed to optimally and quiescently confine the hot plasma.
The stellarator is inherently stable and simple to operate since its performance is controlled only by the fields generated by the external magnets. This removes the need to run a current in the plasma as required by other fusion concepts, which makes them prone to major disruption events that can cause operational failure, damage the device, and degrade fusion performance. Plasma currents also necessitate major equipment, operational, and power requirements to monitor and mitigate these disruptions.
For fusion systems driving a plasma current, a DC transformer is used, which must cycle from start, ramp to a peak, and cease. As a result, the power plant must operate in pulsed mode, resulting in lower power output efficiency, and increased maintenance and downtime from thermal and mechanical cycling stress. In contrast, a stellarator maintains a persistent fusion plasma that produces energy without cessation.
Given that no power is required to drive a current or manage disruption events, a stellarator requires the minimum amount of recirculated energy to maintain the fusion process. This provides the stellarator with a high fusion energy gain factor (Q), an important feature for an efficient electricity generating power plant. The higher the Q, the more economically competitive a fusion power plant will be. Stellarators have the potential to reach infinite Q whereby the energy produced from the fusion plasma becomes self-sustaining requiring no external power to maintain it. This is referred to as "ignition."
Photo by Al Fenn/The LIFE Picture Collection via Getty Images
CC BY-SA 3.0 Max-Planck-Institut für Plasmaphysik
Photo by Al Fenn/The LIFE Picture Collection via Getty Images
twisted magnetic fields keep the fuel particles from
drifting away from where they fuse.
SIMPLE & STABLE
DRIVEN ONLY BY
EXTERNAL MAGNETIC FIELDS
HIGH ENERGY GAIN
A SHORTER PATH TO NET POWER
There are three key factors that determine fusion performance: the density and temperature of the ions undergoing fusion and the energy confinement time - how long the energy is retained in the fusion plasma until it is lost to the surroundings. This is known as the "triple product."
Tokamaks and stellarators are the two leading fusion power systems that have broken away from the pack in the race to reach NET POWER, a milestone comparable to the first powered flight by the Wright brothers. Alternative concepts being pursed by fusion startups are making progress but remain many orders of magnitude lower in performance.
Stellarators have demonstrated high levels of performance in each of the triple product categories:
ions per meter
After many decades of research, the performance of stellarators has been shown to scale very predictably given its simplicity of operation and proven plasma stability at these high ion and electron energy levels. This reduces the risk of unforeseen physics complications that can occur with other fusion concepts when progressing into the net gain energy regimes needed for commercial operation.
A BREAKTHROUGH IN CONFINEMENT
Unlike tokamaks that operate in pulses with susceptibility to disruptions, stellarators can work continuously free of disruptions. However, conventional stellarators have lagged behind tokamak performance because they do not posses the simple circular symmetry of the tokamak, which was better at confining the plasma. This has all changed with the groundbreaking discovery in the 1980s by Jürgen Nührenberg and Allen Boozer of a hidden symmetry in stellarators realized by precisely contouring their magnetic fields so that the various forces causing the particles to drift, cancel each other out. This "quasi symmetry" was the dawn of the modern "optimized" stellarator with its characteristic organic shape.
Because confinement of the plasma in a stellarator is driven solely by the external magnets, modifying their fields has a major impact on performance. To tailor a three-dimensional magnetic field with precisely the right shape to achieve quasi-symmetry requires extensive calculations. Advances in computer modeling code and high performance computing has provided this ability. These powerful tools have resulted in an entirely new class of stellarator optimized for superior confinement and fusion performance.
In 2007, proof for the benefits of magnetic field shaping were first demonstrated with HSX - the world's first optimized stellarator designed and built by Type One co-founders Prof. David Anderson and the German theorists who conceived of and designed the original quasi-helically symmetric stellarator. HSX measured 2.4 meters in diameter and cost USD $7.5 million to build. Due to its optimized configuration, HSX proved superior confinement via strong reductions in neoclassical transport, a previously untamed loss mechanism that causes particles and heat to leak from the plasma. HSX continues to operate and has undergone a recent $7 million power upgrade to extend its research capabilities.
3D shaping to minimize neoclassical transport was further demonstrated with W7-X in Germany, a $1.2 billion statement of conviction for optimized stellarators by the German government. The largest experimental stellarator to date (5.5 m major radius), W7-X went online in 2015 and in 2018, it achieved a world record for stellarator fusion performance with the greatest triple product to date. With cooling system upgrades currently underway, it is targeted in 2022 to reach performance levels comparable to that of tokamaks and at run times of 30 minutes. This will be an unprecedented duration for any fusion system.
OPTIMIZING FOR TURBULENCE
While mitigating neoclassical transport was a major leap forward, the largest loss channel limiting fusion performance in a stellarator is turbulence, which determines the energy confinement time. With turbulence, small eddies cause hot particles from the plasma to escape, reducing the thermal insulation that maintains the rate of fusion at its core.
Given the complexity of the physical process, the analytical tools to address turbulence did not exist at the time that HSX and W7-X were designed. Newly developed and highly sophisticated three-dimensional, gyrokinetic turbulence codes for simulating stellarator physics, combined with high performance computing, have sufficiently advanced to meet this challenge. The resulting stellarator designs generate a new class of high performance plasmas, which will realized in the next Type One stellarator: STARBLAZER I.
Turbulence is the largest source of energy loss
and the last barrier to
achieving net power.
in stellarator design
code enables plasma
turbulence to be
KEY ENABLING TECHNOLOGIES
In addition to providing reliable and abundant power when and where it is needed, a stellarator power plant must be cost-competitive to build and operate. This is now possible due to three transformational capabilities being applied by Type One in collaboration with our academic, national lab, and corporate partners:
Advancements in analytical theory, supercomputing and sophisticated codes uncover previously hidden magnetic field configurations that provide optimal confinement of the plasma for the largest and most efficient power generation.
Generative design with hybrid additive manufacturing, advanced materials, and robotic automation enables the rapid, large scale build of highly optimized, complex-shaped, dimensionally-accurate, and defect-free stellarator components to net shape.
New high-temperature superconducting
(HTS) magnets can carry over 200 times the current carrying capacity of copper wires for a more compact stellarator. It also requires less cooling power than conventional low temperature magnets.
CONFINEMENT FOR NET POWER
With HSX, a quasi-helical stellarator (QHS), there was successful agreement of theory and design to the real-world experiment. We know that QH stellarators can be built and with key physics benefits of the quasi-helical configuration demonstrated. Many of the physics properties of QHS are equivalent to the beneficial features of the tokamak, but without the plasma current instabilities, disruptions, and high recirculating power requirement.
STARBLAZER is a new stellarator currently under design by Type One that incorporates advanced optimization to dramatically reduce both neoclassical and turbulent transport - another world first. Optimizing confinement as a function of magnetic geometry addresses performance at the foundation level to avoid design pathways that would result in a much larger, less versatile, and more expensive power unit.
to control losses from neoclassical and
To extend stellarator fusion performance into the net power regime, STARBLAZER I will determine the optimized 3D-field configuration to be used for building the commercial demonstrator STARBLAZER II, that will reach a target net power factor of over 20X.
Adapted from Phys. Plasmas 26, 082504 (2019); https://doi.org/10.1063/1.5098761
LHD - Large Helical Device Stellarator (Japan - National Institute for Fusion Science)
W7-X - Wendelstein 7-X (Germany - Max Planck Institute for Plasma Physics)
To reduce build time and cost, STARBLAZER I will incorporate generative-designed and additive-manufactured components, which include the magnet assemblies, magnet support shell, heat exchanger, and vacuum vessel:
In parallel, Type One is actively developing the world's first HTS stellarator magnet with a grant from the US Department of Energy ARPA-E BETHE fusion program, in collaboration with the MIT Plasma Fusion Science Center and the University of Wisconsin at Madison.
temperature superconducting stellarator magnet
Type One is building the machine that builds the machine. Type One is developing from the ground up NEBULA - a proprietary large format, selective high precision additive manufacturing platform made for the economical mass production of major fusion components.
AUTONOMOUS FUSION FACTORY
PATH TO A PILOT POWER PLANT
The commercialization campaign has three phases with technical milestones tied to two iterative stellarator builds demonstrating progressive gains in performance, simplification, and cost through the parallel application of 3D magnetic field optimization, industrial additive manufacturing, and non-planar high temperature superconducting electromagnets:
Phase 1 is underway and initiatives include:
● version one in-house build-out of the NEBULA platform
● development of the magnet support shell, vacuum vessel, and divertor
● characterize and qualify AM metal-matrix composites for shielding
with embedded functional particles for thermal, neutron flux, and fatigue resistance.
● physics, conceptual, and engineering design of the STARBLAZER stellarator
● build of the world's first HTS stellarator magnet in collaboration with MIT-PSFC,
Commonwealth Fusion Systems, University of Wisconsin, and funded by the US Dept. of
Phase 2 will see the rapid, lean and low-cost AM build of STARBLAZER I a high-field stellarator devoted to demonstrating net power and the advanced confinement physics needed for deuterium-only operation using the advanced 3D field-optimized configuration.
Phase 3 executes on the build of STARBLAZER II which incorporates extensive AM components, HTS magnets, and an integrated shield/heat exchange blanket using advanced ultra supercritical water, tungsten carbide and F82H MMC steel. This serves as the most compact and durable radial build.
The keystone deliverable of STARBLAZER II will be the demonstration of over 20 times net power generation. This will be a a "triple net" measure that factors in total "wall plug" input energy used by the power system, the losses from converting the fusion energy into electricity, as well as recirculating energy fed back into the system to maintain the process.
TWENTY TIMES THE ENERGY
NEEDED TO ACHIEVE
STARBLAZER II will be paired with an advanced and well established steam cycle technology that employs supercritical water (s-H20) as the working fluid to drive a high-heat turbine for a power conversion efficiency target of >45%.
Although deuterium fuel is economically available in large quantities from major industrial gas suppliers, Phase 3 will demonstrate an on-site, end-to-end, water-fusion-electricity solution, using a Liquid Phase Catalytic Exchange (LPCE) column to highly concentrate liquid deuterium from water and extract it as a gas using PEM-based electrolysis. In regions with multiple Type One power plant installations, the use of a centralized deuterium fuel production facility can be deployed to service multiple power plants and well as produce clean hydrogen for transport and industrial uses.
The stellarator power unit is designed to provide a steady output of baseload power at its rated capacity with surplus electricity able to be stored as hydrogen for instant grid balancing or sold for fuel cell transportation and industrial processes.
ECONOMICAL POWER PLANT
DESIGNING FOR RAPID & WIDESPREAD ADOPTION
500MWe D-D STELLARATOR
UNIT & HEAT EXCHANGER
SUPERCRITICAL H20 STEAM CYCLE WITH TURBINE BYPASS LOAD FOLLOWING
SURPLUS ELECTRITCY STORED AS HYDROGEN FOR INSTANT GRID BALANCING OR SALE (OPTIONAL)
Stellarator physics are inherently suited for power plant operation:
LOW RECIRCULATING POWER
STEADY STATE OPERATION
NO CURRENT DISRUPTIONS
STABLE PLASMA OPERATION
HIGH DENSITY OPERATION
MAXIMIZE SYSTEM OUTPUT
In addition, to disrupt carbon-based fuels, a fusion power plant must meet a combination of low capital costs, rapid construction time, low downtime, and ease of maintenance. The combination of additive manufacturing, high magnetic field, and supercritical water thermal cycle offers the best path for a stellarator plant to achieve these objectives. The following non-subsidized costs are targeted for 10th-of-a-kind power units and nth-of-a-kind balance of plant:
CAPITAL COST (FUSION ISLAND)
FIRST WALL LIFETIME
COST OF ELECTRICITY
GENERATION PER POWER UNIT
TARGETING SIMPLICITY & LONGEVITY
The force of gravity at the core of the Sun creates tremendous density and unending confinement time that allows hydrogen to fuse at only 15 million degrees. In a fusion device, such conditions are not attainable, necessitating temperatures in the range of 100 million degrees. In addition, hydrogen is 24 orders of magnitude less reactive to fuse than its neutron-rich isotopes deuterium and tritium - the most viable fusion fuels for use here on Earth.
DEUTERIUM-TRITIUM FUEL CYCLE
The easiest fuel combination to fuse is deuterium with tritium (D-T) to create helium and a highly energetic 14 MeV neutron. Tritium does not exist in nature has to be bred in the "blanket" that surrounds the plasma using lithium and the neutrons generated during the fusion process. With 80% of the energy carried by the neutrons, part of the blanket includes a working fluid that slows down the neutrons to thermal energies, and then transfers that heat to a power conversion cycle. Given the high energies of these neutrons and the additional layer required for tritium breeding, blankets used for the D-T fuel cycle have to be over one meter thick. Additionally, structural materials need to operate at very high temperatures of over 550 degrees Celsius and withstand damage from the high energy neutrons, necessitating more frequent replacement of plasma facing components.
CATALYZED DEUTERIUM-DEUTERIUM FUEL CYCLE
The demonstrated high density, high beta, and large power gain factor of stellarators paired with high field, facilitates the potential use of deuterium as the only fuel. It is "catalyzed" since the helium-3 produced from the primary D-D reaction is subsequently fused with deuterium in secondary reactions to produce more energy and helium. Unlike D-T, the majority of the fusion energy is not carried by the energetic neutrons, but in the charged particles that have undergone fusion:
Cat D-D Charged Particle Chain
PRODUCED TRITIUM AND HELIUM 3 FUSED WITH
ADDITIONAL DEUTERIUM TO BECOME HELIUM
The use of Cat D-D requires thirty-five times greater confinement performance than the D-T cycle, but it removes numerous cost, complexity, and engineering challenges associated with the D-T system, such as readily available fuel and no need for a tritium breeding blanket or tritium recovery fueling system. Because a much lower neutron flux is generated with tritium extraction, a number of benefits are realized:
● 55% thinner build between the magnets and the plasma for a more effective
application of the confining fields and a more compact device
● greatly extended service life of components (from years to decades)
● improved ease of maintenance
● increased operational uptime
● reduced neutron activation of materials suitable for recycling and clearance
● no dependency on exotic or limited mined resources
● easier to license by regulatory agencies
Fuel cycle R&D will asses the use of ion cyclotron power to pump out a portion of the tritium before it fuses to further reduce the number of 14 MeV neutrons and increase the lifetime of components. The tritium is stored and naturally converts into helium-3 (half-life of 12.3 years), which is a fuel that produces hydrogen and helium when fused with deuterium and no neutrons.
The viability of Cat D-D as a fuel option for commercial operation will be experimentally assessed based on the confinement physics demonstrated with STARBLAZER I.
FOR RAPID MARKET CAPTURE
Revenues will be generated through the mass production and sale of stellarator power units produced from Type One Staryards strategically located in major markets to remove the high cost and time of transporting large components overseas. A blend of pre-assembled and in inventory components with just-in-time, rapid additive manufacturing will be employed to meet a 2-year plant installation and commissioning target. To participate in revenues from the sale of electricity (~$1.3 trillion per year addressable market), Power Purchase Agreements (PPA) will be secured with utilities and partner deployment firms specializing in Engineering, Procurement, Construction (EPC), as well as Operating and Maintenance (O&M).
Approximately 300 quadrillion BTUs ("quads") of new energy are required by 2050 (US IEA) to meet demand, raising total global energy consumption to 911 quads. This translates to roughly $50 trillion in cumulative investments in generation over the same period. Carbon-based energy is projected to lose 11% of market share during this period but will still comprise a majority share of the energy mix at 69%. This amounts to 125 quads in new carbon-based energy generating 3.6 billion tonnes of additional CO2 per year in 2050.
Type One will initially focus on intercepting new natural gas, coal, and diesel generating capacity in the 1 GWe and greater range and replacement of decommissioned plants for heat and electricity in the emerging markets of OECD Asia. This market represents:
● the largest and fastest-growing region in the world for energy consumption (a projected
70% increase from 2018 to 2050)
● new baseload power plants averaging 820 MWe (natural gas) to 1100 MWe (nuclear)
● high fractions of fossil fuels in their energy mix (e.g. China and India draw more than 70%
of their electricity from coal - US EIA).
Type One will spearhead fusion industry-led initiatives for regions to adopt regulations and licensing appropriate for fusion (already underway in the US), provide government loan guarantees on construction, and offer fusion subsidies to utilities.
WITH HIGH % OF
MANDATED COAL RETIREMENT
Making up more than half of global energy consumption, the biggest challenge is the decarbonization of industry, which include energy intensive applications such as making steel and cement, desalinization, and upcoming atmospheric decarbonization deployments.
PROCESS & DISTRICT
High heat for cement, steel, glass, chemicals, and other uses is 32% of global energy use.
Currently, helium is obtained from natural underground reserves that are dwindling.
By 2050, over half of the global population will live in water stressed areas.
Long half-life isotopes are produced by only 8 nuclear reactors and flown worldwide.
Direct air capture requires a whopping
8.8 gigajoules of energy per ton of CO2.
95% of hydrogen fuel is made with methane, a fossil fuel input that emits carbon dioxide.
POWERING THE HYDROGEN ECONOMY
Currently, 95% of the world's hydrogen fuel is made by reforming methane, which is energy intensive, requires fossil fuel inputs and emits carbon dioxide. In contrast, hydrogen-from-fusion can be economically generated at industrial scale and stored as an emissions-free byproduct of both the deuterium extraction process and fusion reactions. These factors will be a major cost and ecological enabler for the proliferation of hydrogen applications in stored heat and power, industry feedstock, and fuel cell electric vehicles (a 2018/2020 KPMG study discovered that 78% of automobile executives think that hydrogen fuel cell electric vehicles will be the future and 84% think that FCEVs will experience their breakthrough in industrial transportation – particularly where batteries become too heavy for heavy duty trucks above 34 tonnes).
CHIEF EXECUTIVE OFFICER
For over 25 years, Randall has been a serial startup entrepreneur, business development director, and R&D project manager across numerous technology sectors from concept to acquisition. A fusion energy enthusiast from the age of eight, Randall has been contributing to the growth of the fusion R&D community full time since 2014, serving in various leadership capacities that focus on broadening the fusion ecosystem of research, private finance, industry collaboration, government support, and NGO advocacy.
Randall is on the Advisory Board of the Fusion Industry Association, the representative body of the international fusion startup community, and an Adjunct Fellow of the American Security Project.
Dr John Canik
CHIEF SCIENCE OFFICER
John received his PhD in Plasma Physics from the University of Wisconsin-Madison and led numerous stellarator studies at the HSX Plasma Laboratory, including landmark experiments validating the ability of optimized stellarators to reach new levels of confinement performance. In 2007, John went to work at Oak Ridge National Laboratory (ORNL) under a prestigious Wigner Fellowship. John then headed the ORNL Plasma Physics Theory Group and served as the interim Director of the ORNL Fusion Energy Division from 2019 to 2020. In 2021, John received the Fusion Power Associates Excellence in Fusion Engineering Award.
CHIEF TECHNOLOGY OFFICER
Paul has 30 years of electrical engineering and company management across a range of high technology sectors including satellite control systems, nuclear detection instruments, semiconductors, electric bikes, pulsed power, and fusion energy. As an application engineer, he has taught senior engineers in high tech companies how to incorporate new technology into their designs. He is an energetic team builder and solutions-driven leader that's battle hardened to take on the challenges a startup can face.
Prof. David Anderson
David received his PhD in engineering from the University of Wisconsin in 1984 and has been a world leader in stellarator R&D for over thirty years. Within the UW-Madison College of Engineering, he established the HSX Plasma Laboratory and successfully designed, built and operated the world's first optimized stellarator, which included the in-house manufacture of the complicated magnet coils to precision tolerances. David led the engineering and experimental campaign that proved the impact of optimized stellarators to dramatically improve confinement.
David's career in plasma physics and controlled fusion includes various publications, awards and lectures for numerous graduate level courses in plasma physics and electrodynamics.
Prof. Chris Hegna
Chris is the director of the University of Wisconsin Center for Plasma Theory and Computation and is involved in the research activities of three magnetic confinement experiments, the HSX Plasma Laboratory, Pegasus Toroidal Experiment (PTE), and the Madison Symmetric Torus (MST). His primary field is theoretical plasma physics with an emphasis on plasma confinement using magnetic fields.
Chris is heavily involved in the U.S. fusion science program by serving on a number of workshop and conference organization committees, review panels and program advisory committees. In 2014, he received the Excellence in Plasma Physics Research Award by the American Physical Society.
SPONSORED RESEARCH CONTRIBUTORS
Asst. Prof. Lianyi Chen
ADDITIVE MANUFACTURING - MATERIAL SCIENCE
Asst. Prof. Lianyi Chen holds a Ph.D. in Materials Science and Engineering from Zhejiang University and joint affiliations with the Metals Design and Manufacturing Laboratory at the University of Wisconsin-Madison, the Missouri S&T Department of Materials Science and Engineering, Department of Mechanical and Aerospace Engineering, and Center for Aerospace & Manufacturing Technologies.
Lianyi's expertise is at the intersection of AM manufacturing, materials science, and nanotechnology. His specializations include new materials, metallurgy, and processes for metal additive manufacturing, metals nanoprocessing, smart manufacturing using advanced sensing and control technologies, metal matrix nanocomposites, lightweight and refractory metals, metallic glasses and in-situ microstructure characterization.
Lianyi has developed a customized laser powder bed AM system and laser blown powder DED system for in-situ high-speed x-ray imaging/diffraction research, as well as led multiple AM projects funded by NSF, DOE’s KCNSC, and Boeing. He has published over 50 papers in peer-reviewed journals, including 1 in Nature, 1 in Nature Communications, 2 in Physical Review Letters, and 4 in Acta Materialia. He is also an inventor of 6 patents.
Dr. Ben Faber
Ben holds a PhD in Physics for the University of Wisconsin-Madison, and is an expert on turbulence in stellarator devices. A computational physicist by training, he currently holds a staff scientist position in the Department of Engineering Physics at UW-Madison working on building new tools and infrastructure for stellarator optimization, with a focus on turbulent optimization.
Luquant is an Electrical Engineering PhD student at UW-Madison interested in stellarator design and manufacturing. He has been a member of the HSX Plasma Laboratory for nearly four years, recently joining the lab as a graduate student. His current work is focused on improving the design of stellarator coils using computational methods.
Dr. Don Spong
STELLARATOR PLASMA AND COMPUTATIONAL PHYSICS
Don is a Distinguished R&D staff member in the Theory and Modeling group within the Fusion Energy Division at Oak Ridge National Laboratory. He received his PhD in Nuclear Engineering - Plasma Physics from the University of Michigan. Don’s interests are in energetic particle confinement/instabilities, runaway electron physics, and neoclassical transport in 3D systems. He helped develop the stellarator optimization and analysis methods used for the QPS/NCSX compact stellarator projects. He has served two appointments as a visiting professor at the institute (NIFS) which operates Japan’s largest stellarator project (LHD). He currently serves as the topical group leader for the energetic particle physics ITPA group that advises ITER.
Thomas is an Electrical Engineering PhD student at the University of Wisconsin-Madison researching for Type One and the HSX Stellarator Laboratory. His research focuses on the optimization of stellarator coils, specifically how to find favorable equilibrium fields with less complicated coils. He also optimizes stellarator coils to be more compatible with advanced fabrication methods.
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