A5056224732- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Spacecraft and Cryogenic Technologies
- Laser-Plasma Interactions and Diagnostics
- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Gyrotron and Vacuum Electronics Research
- Cold Fusion and Nuclear Reactions
- Korean Peninsula Historical and Political Studies
- Ionosphere and magnetosphere dynamics
- Nuclear and radioactivity studies
- Graphite, nuclear technology, radiation studies
- Fluid Dynamics Simulations and Interactions
- International Science and Diplomacy
- Parallel Computing and Optimization Techniques
- Laser-induced spectroscopy and plasma
- Heat Transfer and Optimization
- Crystallography and Radiation Phenomena
- Atomic and Molecular Physics
- Particle Detector Development and Performance
- X-ray Spectroscopy and Fluorescence Analysis
Princeton Plasma Physics Laboratory
2015-2025
Princeton University
2015-2017
Stellar Solutions (United States)
2017
University of Wisconsin–Madison
2012
The engineering limits of plasma-facing components (PFCs) constrain the allowable operational space tokamaks. Poorly managed heat fluxes that push PFCs beyond their not only degrade core plasma performance via elevated impurities, but can also result in PFC failure due to thermal stresses or melting. Simple axisymmetric assumptions fail capture complex interaction between three-dimensional (3-D) geometry and two-dimensional 3-D plasmas. This results fusion systems must either operate with...
The use of Highly Oriented Pyrolytic Graphite (HOPG) reflectors is often proposed in the design X-ray Crystal Spectroscopy (XCS) diagnostic systems for next-generation tokamak devices, including ITER project. This study introduces an experimental based on X-Ray Diffractometry (XRD) method to evaluate performance HOPG reflectors. provides both angular responses and reflectivities A demonstrative XRD experiment conducted, details are introduced. enables precise studies reflectors, facilitating...
A high-fidelity synthetic diagnostic has been developed for the ITER core x-ray crystal spectrometer based on ray tracing. This used to model expected performance of diagnostic, aid in design, and develop engineering tolerances. The is tracing using recently xicsrt code includes a fully three-dimensional representation computer aided design. modeled components are: plasma geometry emission profiles, highly oriented pyrolytic graphite pre-reflectors, spherically bent crystals, pixelated...
The design of the ITER low-field side reflectometer (LFSR) has matured to a complete end-to-end preliminary design. LFSR will supply three important plasma measurements: (1) electron density profile, (2) fluctuations, and (3) poloidal rotation. Simultaneous measurements quantities are enabled by an array six monostatic antennas which inject from equatorial port on outboard vessel. Low-loss transmission lines, consisting corrugated, overmoded waveguide miter bends, transmit 30–165 GHz, O-...
Numerical simulations of the ITER Diagnostic First Wall (DFW) were performed using ANSYS workbench. During operation DFW will include solid main body as well liquid coolant. Thus thermal and hydraulic analysis was conjugated heat transfer approach, in which resolved both parts, simultaneously fluid dynamics only part. This approach includes interface between part system. Analysis CFX software. software allows solution equations part, flow Coolant assumed turbulent Reynolds averaged...
The Diagnostic First Walls (DFWs) were designed to handle the plasma nuclear and radiant heating along with electro-magnetic loading induced from disruptions. DFWs also provide custom viewing apertures for diagnostics within. Consequently, contain numerous complex water cooling channels are per ITER SDC-IC design by analysis.This paper presents analyses of Upper Port proceeding a final review. finite element (FEAs) performed include neutronics, radiative heating, coupled fluid dynamics heat...
ITER is the world's largest fusion device currently under construction in South of France with >50 diagnostic systems to be installed inside port plugs (PPs), interspace (IS), or cell region various ports. The plasma facing first wall (DFW) and its supporting shield modules (DSM) are designed protect front-end diagnostics from neutron radiation, while providing apertures for access plasma. design plug structures including DFW DSM largely driven by electromagnetic loads included on PP...
Development of the port-based diagnostic and service system integration in Tokamak has been a challenging task for ITER (Nuclear Facility INB-174) engineering. Port is demanding more work on ex-vessel to identify electromagnetic thermal nuclear environment interspace port cell regions. Protecting equipment & regions poses considerable engineering constraints. This paper will focus normal accidental environmental conditions such as seismic, magnetic field, radiation, pressure, temperature...
The magnetic pitch angle and the magnitude from reversed field pinch plasmas in Madison symmetric torus (MST) have been routinely obtained fully resolved motional Stark effect (MSE) spectrum analyses. Recently, fit procedure has improved by initializing constraining parameters based on MSE model atomic data analysis structure. A collisional-radiative with level populations nlm-resolved up to n = 4 a simple Born approximation for ion-impact cross sections is used this analysis. Measurement...
ITER is an international project under construction in France that will demonstrate nuclear fusion at a power plant-relevant scale. The Toroidal Interferometer and Polarimeter (TIP) Diagnostic be used to measure the plasma electron line density along 5 laser-beam chords. This line-averaged measurement input feedback-control system. TIP considered primary diagnostic for these measurements, which are needed basic machine control. Therefore, system reliability & accuracy critical element TIP’s...
Initial China Fusion Engineering Test Reactor (CFETR), blanket design, includes water-cooled ceramic breeder (WCCB) operating in pre-superheated regime. This condition allows efficient cooling; however it requires accurate control and analysis to avoid zones with excessive heat flux. Analysis of the coolant flow transfer CFETR Pre-Superheated Blanket was performed using ANSYS CFX included: 3D analysis, external volumetric surface heating effect, two-phase wall boiling. ASIPP CAD Model...