Zeke Unterberg

Ezekial A Unterberg

Distinguished R&D Scientist | Fusion Materials R&D Lead

Contact

865.576.6390 | UNTERBERGEA@ORNL.GOV

All Publications

Use of isotopic tungsten tracers and a stable-isotope-mixing model to characterize divertor source location in the DIII-D metal rings campaign

HELIOS: A Helium Line-ratiO Spectral-monitoring Diagnostic for High Resolution Plasma Profiles near the ICRH Antenna on TEXTOR

Global Particle Balance Measurements in DIII-D H-mode Discharges...

A scoping study of far-SOL main-wall protection limiters for steady-state operation of compact pilot plant tokamaks

Predictive outlook for experiments resolving prompt vs local redeposition of high-Z materials in tokamaks

HEAT Simulation and IR Data Comparison for ST40 Plasma-Facing Components

DIII-D research to provide solutions for ITER and fusion energy

WEST full tungsten operation with an ITER grade divertor

Investigation of materials for radio frequency antenna plasma facing components

Multi-physics modeling of tungsten collector probe samples during the WEST C4 He campaign

Filterscope Techniques for Parasitic Signal Screening

Dependence of high-Z redeposition on the field-to-surface pitch angle and other sheath parameters in tokamaks

Design and analysis of actively-cooled, edge-transport diagnostic for long-pulsed operation in WEST

Calibration improvements expand filterscope diagnostic use

Oak Ridge National Laboratory Official TM Cover: Development and Qualification of Tungsten Reference Materials for LA-ICP-MS

The effectiveness of D2 pellet injection in reducing intra-ELM and inter-ELM tungsten divertor erosion rates in DIII-D during the Metal Rings Campaign

Refining light impurity content estimates at the lower divertor based on experimental data in WEST

13C surface characterization of midplane and crown collector probes on DIII-D

Development of an Integrated Multidiagnostic to Assess the High-Z Impurity Fluxes in the Metallic Environment of WEST Using IMAS

OEDGE modeling of far-SOL tungsten impurity sources and screening in WEST

Characterizing W sources in the all-W wall, all-RF WEST tokamak environment

3D ion gyro-orbit heat load predictions for NSTX-U

Development of an Integrated Multidiagnostic to Assess the High-Z Impurity Fluxes in the Metallic Environment of WEST Using IMAS

Initial results from boron powder injection experiments in WEST lower single null L-mode plasmas

Developing solid-surface plasma facing components for pilot plants and reactors with replenishable wall claddings and continuous surface conditioning. Part A: concepts and questions