Jeremy D Lore

Jeremy D Lore

Contact

865.574.0982 | LOREJD@ORNL.GOV

All Publications

Feasibility of fusion plasma burn control via real-time, sub-divertor neutral gas isotopic and compositional analysis
A scaling law of the neutral penetration length and Balmer-α wing shape in high-temperature plasmas
Power balance and divertor asymmetries in the Super-X divertors of MAST-U using SOLPS-ITER
Integrated modeling of RF-Induced Tungsten Erosion at ICRH Antenna Structures in the WEST Tokamak...
Evolution of radiation profiles in a strongly baffled divertor on MAST Upgrade...
Integrated modeling of boron powder injection for real-time plasma-facing component conditioning...
Radiofrequency sheath rectification on WEST: application of the sheath-equivalent dielectric layer technique in tokamak geometry
Simulation of plasma and neutral transport in PISCES-RF using SOLPS-ITER
WEST full tungsten operation with an ITER grade divertor
DIII-D research to provide solutions for ITER and fusion energy
Experimental investigation of steady state power balance in double null and single null H mode plasmas in MAST Upgrade
Evaluation of SPARC divertor conditions in H-mode operation using SOLPS-ITER
Multi-physics modeling of tungsten collector probe samples during the WEST C4 He campaign
High performance power handling in the absence of an H-mode edge in negative triangularity DIII-D plasmas
Conceptual design of a Doppler spectrometer for 102 m/s cross-field flows in tokamak divertors...
Full time-dependent SOLPS-ITER simulation of the SPARC tokamak: actuator design for particle and divertor condition control *
Exploring the effect of ELM and code-coupling frequencies on plasma and material modeling of dynamic recycling in divertors
Analysis and design of fast flow liquid Li divertor for fusion nuclear science facility (FNSF) using coupled plasma boundary and LM MHD/heat transfer codes*
Impact of gas injection location and divertor surface material on ITER fusion power operation phase divertor performance assessed with SOLPS-ITER
Progress In A US-Based Liquid Metal Plasma-Facing Component Design Activity For A Fusion Nuclear Science Facility
INTEGRATED PLASMA AND ENGINEERING DESIGN AND ASSESSMENT FOR TOKAMAK REACTOR COMPONENTS...
TIME-DEPENDENT SOLPS-ITER SIMULATIONS OF THE TOKAMAK PLASMA BOUNDARY FOR MODEL PREDICTIVE CONTROL
Time-Dependent Boundary Modeling to Inform Design of SPARC Diagnostic and Actuators
Analysing the effects of heating and gas puffing in Proto-MPEX helicon and auxiliary heated plasmas *
Compression of tokamak boundary plasma simulation data using a maximum volume algorithm for matrix skeleton decomposition

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