A Hungarian-algorithm solver for the signed assignment problem disambiguates randomly wired and polarized ITER magnetic sensors down to SNR 50 with C>0.97 on regular first-wall arrays.
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10 Pith papers cite this work. Polarity classification is still indexing.
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physics.plasm-ph 10years
2026 10representative citing papers
FIREFLY offers simplified approximations for divertor heat loads and particle exhaust to speed up design evaluation in magnetic confinement fusion.
JOREK simulations demonstrate that increasing nitrogen seeding moves the X-point radiator upwards in ASDEX Upgrade while decreasing it moves the radiator downwards.
Core-edge integrated modeling finds argon-seeded ARC H-modes achieve 750-1000 MW fusion power with detached divertors below 2 eV, outperforming neon seeding which yields 600-850 MW and weaker H-mode access.
Design study proposing a compact negative-triangularity tokamak with REBCO magnets targeting 40 MW fusion power, Q=1.3, and $1.6B cost via integrated plasma, neutronics, and economic modeling.
A materials-limited HTS tokamak design achieves net electricity for off-grid uses at 130 MW fusion power with self-consistent high-field plasma parameters and detached divertor operation.
SOLPS-NN is a fully connected neural network surrogate trained on SOLPS-ITER simulations that predicts spatial plasma profiles and indicates access to detachment with experimental trends.
Toroidal flux should replace poloidal flux as the radial coordinate in separatrix-bounded tokamak plasmas to simplify equilibria and reduce q_95 sensitivity to central current profiles.
The MPEX AI Digital Twins project reports that its two phase-I AI milestones for hot-spot control and damage assessment are on track for June 2026 demonstration.
citing papers explorer
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Disambiguation of magnetic sensors in ITER
A Hungarian-algorithm solver for the signed assignment problem disambiguates randomly wired and polarized ITER magnetic sensors down to SNR 50 with C>0.97 on regular first-wall arrays.
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FIREFLY: heat load and particle exhaust approximations for rapid evaluation of divertor designs
FIREFLY offers simplified approximations for divertor heat loads and particle exhaust to speed up design evaluation in magnetic confinement fusion.
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JOREK simulations of the X-point radiator formation and its movement in ASDEX Upgrade
JOREK simulations demonstrate that increasing nitrogen seeding moves the X-point radiator upwards in ASDEX Upgrade while decreasing it moves the radiator downwards.
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Core-edge integrated modeling of ARC: on the effect of impurity transport and detachment conditions
Core-edge integrated modeling finds argon-seeded ARC H-modes achieve 750-1000 MW fusion power with detached divertors below 2 eV, outperforming neon seeding which yields 600-850 MW and weaker H-mode access.
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Compact Experimental Negative TriAngUlarity Reactor (CENTAUR): A design study for a compact, affordable breakeven tokamak
Design study proposing a compact negative-triangularity tokamak with REBCO magnets targeting 40 MW fusion power, Q=1.3, and $1.6B cost via integrated plasma, neutronics, and economic modeling.
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Yinsen: A low power density HTS tokamak fusion reactor for marine and off-grid applications
A materials-limited HTS tokamak design achieves net electricity for off-grid uses at 130 MW fusion power with self-consistent high-field plasma parameters and detached divertor operation.
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Deep-Learning based surrogate models for plasma exhaust simulations -- SOLPS-NN
SOLPS-NN is a fully connected neural network surrogate trained on SOLPS-ITER simulations that predicts spatial plasma profiles and indicates access to detachment with experimental trends.
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The toroidal flux and separatrix effects in tokamaks
Toroidal flux should replace poloidal flux as the radial coordinate in separatrix-bounded tokamak plasmas to simplify equilibria and reduce q_95 sensitivity to central current profiles.
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MPEX AI Digital Twins Milestone Report
The MPEX AI Digital Twins project reports that its two phase-I AI milestones for hot-spot control and damage assessment are on track for June 2026 demonstration.
- Non-Ambipolarity of Microturbulent Transport