A5044282386- Magnetic confinement fusion research
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Advanced Battery Technologies Research
- Nuclear Materials and Properties
- Laser-induced spectroscopy and plasma
- Space Exploration and Technology
- Solar and Space Plasma Dynamics
- Planetary Science and Exploration
- Ionosphere and magnetosphere dynamics
- Spacecraft and Cryogenic Technologies
- Laser-Plasma Interactions and Diagnostics
- Pulsed Power Technology Applications
- Geology and Paleoclimatology Research
- Geophysical Methods and Applications
- Scientific Measurement and Uncertainty Evaluation
- Superconductivity in MgB2 and Alloys
- Plasma Diagnostics and Applications
- Cold Fusion and Nuclear Reactions
- Radiation Effects in Electronics
- Silicon and Solar Cell Technologies
- Graphite, nuclear technology, radiation studies
- Molten salt chemistry and electrochemical processes
Princeton Plasma Physics Laboratory
2014-2024
Princeton University
2016-2022
University of Idaho
2011
University of California, Los Angeles
2003-2011
Los Alamos National Laboratory
2011
University of Illinois System
2003
Fusion Academy
1989-2003
Fusion (United States)
1989-2003
University of Illinois Urbana-Champaign
1992-1995
Massachusetts Institute of Technology
1989-1991
Abstract The objectives of NSTX-U research are to reinforce the advantages STs while addressing challenges. To extend confinement physics low- A , high beta plasmas lower collisionality levels, understanding transport mechanisms that set performance and pedestal profiles is being advanced through gyrokinetic simulations, reduced model development, comparison NSTX experiment, as well improved simulation RF heating. develop stable non-inductive scenarios needed for steady-state operation,...
The ITER design, and future reactor designs, depend on divertor 'detachment,' whether partial, pronounced or complete, to limit heat flux plasma-facing components surface erosion due sputtering. It would be valuable have a measure of the difficulty achieving detachment as function machine parameters, such input power, magnetic field, major radius, etc. Frequently parallel flux, estimated typically proportional Psep/R PsepB/R, is used proxy for this difficulty. Here we argue that impurity...
It has long been recognized that volumetric dissipation of the plasma heat flux from a fusion power system is preferable to its localized impingement on material surface. Volumetric mitigates both anticipated very high and intense particle-induced damage due sputtering. Recent projections tokamak demonstration plant suggest an immense upstream parallel flux, order 20 GW m−2, implying fully detached operation may be requirement for success power. Building pioneering work use lithium by...
Fusion power plants are likely to require near complete detachment of the divertor plasma from target plates, in order have both acceptable heat flux at avoid prompt damage and also temperature surface, minimize long-term erosion. However hydrogenic impurity puffing experiments show that detached operation leads easily x-point MARFEs, impure plasmas, degradation confinement, lower helium pressure exhaust. The concept Lithium Vapor Box Divertor is use local evaporation strong differential...
AbstractThe ARIES research program is a multi-institutional effort to develop several visions of tokamak reactors with enhanced economic, safety, and environmental features. Three are currently planned for the program. The ARIES-I design DT-burning reactor based on "modest" extrapolations from present physics database relies either existing technology or which trends already in place, often programs outside fusion; ARIES-II will employ potential advances physics; ARIES-III conceptual D-3He...
Following ELMy H-mode experiments with liquid metal divertor target on the COMPASS tokamak, we predict behavior of a similar Upgrade, where it will be exposed to surface heat fluxes even higher than those expected in future EU DEMO attached divertor.We simulate conduction, sputtering, evaporation, excitation and radiation lithium tin area.Measured high-resolution data from tokamak were rescaled towards Upgrade based many established scalings.Our simulation then yields amount released which...
A detached divertor is predicted to be necessary handle the heat fluxes of a demonstration fusion power plant. The lithium vapor box localizes dense cause stable detachment. This localization formed by local evaporation and nearby condensation. We provide simulation flow using SPARTA Direct Simulation Monte Carlo (DSMC) code. Simulations baffled divertor's mass are within factor two an ideal-gas choked nozzle calculation. Lithium density each chamber given for 200 MW input Demo-scaled...
Scheduled maintenance is likely to be lengthy and therefore consequential for the economics of fusion power plants. The strategy that maximizes economic value a plant depends on internal factors such as cost durability replaceable components, frequency duration blocks, external electricity system in which operates. This paper examines plants with various properties decarbonized United States Eastern Interconnection circa 2050. Seasonal variations supply demand mean certain times year,...
Abstract This study demonstrates that using spin-polarized deuterium-tritium (D-T) fuel with more deuterium than tritium can increase burn efficiency (TBE) by at least an order of magnitude without compromising fusion power output, compared to unpolarized fuel. Although previous studies show a low fraction enhance TBE, this strategy resulted in reduced density. The surprising improvement TBE fixed reported here is due the increasing nonlinearly decreasing but density roughly linearly D-T...
The Advanced Reactor Innovation and Evaluation Study (ARIES) is a community effort to develop several visions of the tokamak as fusion power reactor. aims are determine its potential economics, safety, environmental features identify physics technology areas with highest leverage for achieving best authors focus on ARIES-1 design. Parametric systems studies show that optimum first stability has relatively low plasma current ( approximately 12 MA), high aspect ratio 4-6), magnetic field 24 T...
Results are presented for one- and two-dimensional (2D) edge plasma transport simulations strong injection of lithium (Li) in the divertor region a tokamak. The model includes scrape-off layer regions, and, 2D, small inside magnetic separtrix. Equations solved density momentum deuterium/tritium (DT) species all three charge states Li, addition to separate ion electron energy equations via UEDGE code. also included DT Li gas species. Lithium is injected from side walls or plate, implying that...
The lithium vapor box divertor is a potential solution for power exhaust in toroidal confinement devices. plasma interacts with localized, dense cloud of vapor, leading to volumetric radiation, cooling, recombination, and detachment. To minimize contamination the core plasma, condensed on cool (300–400°C) baffles upstream detachment point. Before implementing this device slot geometry, we consider an experiment scaled baffled-pipe geometry high-power linear Magnum-PSI. Three 15 cm-scale open...
Abstract Shaping a tokamak plasma to have negative triangularity may allow operation in an edge-localized mode-free L-mode regime and with larger strike-point radius, ameliorating divertor power-handling requirements. However, the shaping has potential drawback form of lower no-wall ideal beta limit, found using MHD codes chease dcon . Using new fusion systems code faroes , we construct steady-state DEMO2 reactor model. This model is essentially zero-dimensional neglects variations physical...
The lithium vapor-box divertor is a possible fusion power exhaust solution. It uses condensation pumping to create gradient of vapor density in slot; this should allow stable detachment front without active feedback. As initial explorations the concept, two test stands which take form three connected cylindrical stainless steel boxes are being developed: one plasma at PPPL, models evaporation and flow; for linear device Magnum-PSI (at DIFFER Eindhoven, Netherlands) ability cloud induce...
The lithium vapor box divertor is a concept for handling the extreme heat fluxes in magnetic fusion devices. In baffled slot divertor, plasma interacts with dense cloud of Li which radiates and cools plasma, leading to recombination detachment. Before testing on tokamak, should be validated: we plan study detachment redistribution by laboratory experiments. Mass changes temperatures are measured validate direct simulation Monte Carlo model neutral Li. initial experiment involves 5 cm...
In the coming decades, United States aims to undergo an energy transition away from fossil fuels and toward a fully decarbonized power grid. There are many pathways that US could pursue this objective, each of which relies on different types generating technologies provide clean reliable electricity. One potential contributor these is advanced nuclear fission, encompasses various innovative reactor designs. However, little known about how cost-competitive reactors would be compared other...