A5004077634- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Composite Structure Analysis and Optimization
- Topology Optimization in Engineering
- Nuclear Materials and Properties
- Laser-Plasma Interactions and Diagnostics
- Gyrotron and Vacuum Electronics Research
- Spacecraft and Cryogenic Technologies
- Nuclear reactor physics and engineering
- Engineering Applied Research
- Structural Analysis and Optimization
- Aeroelasticity and Vibration Control
- Composite Material Mechanics
- Structural Analysis of Composite Materials
- Metal and Thin Film Mechanics
- Engineering Education and Curriculum Development
- Hydraulic and Pneumatic Systems
- Rocket and propulsion systems research
- Advanced Thermodynamic Systems and Engines
- Engineering Education and Pedagogy
- Ionosphere and magnetosphere dynamics
- Heat Transfer Mechanisms
Oak Ridge National Laboratory
2015-2024
Government of the United States of America
2022
University of Tennessee at Knoxville
2002-2020
University of Evansville
2013
Agilent Technologies (United States)
2008-2009
University of Michigan–Ann Arbor
1995
The availability of future fusion devices, such as a nuclear science facility or demonstration power station, greatly depends on long operating lifetimes plasma facing components in their divertors. ORNL is designing the Material Plasma Exposure eXperiment (MPEX), superconducting magnet, steady-state device to address material interactions reactors. MPEX will utilize new highintensity source concept based RF technology. This allow experiment cover entire expected conditions divertor reactor....
Linear plasma generators are cost effective facilities to simulate divertor conditions of present and future fusion reactors. They used address important R&D gaps in the science material interactions towards viable facing components for Next generation have be able access expected on targets ITER devices. The steady-state linear device MPEX will this regime with electron temperatures 1–10 eV densities . resulting heat fluxes about 10 MW is designed deliver those a novel Radio Frequency...
A set of new water-cooled divertor components is being designed for the Wendelstein 7-X stellarator to protect edges primary plasma facing during bootstrap current evolution (~ 40 s). These components, referred as scraper elements (SEs), will intercept field lines and associated heat flux that would otherwise overload main target in certain operational scenarios. The SEs are calculated experience peak fluxes ~15-16 MW/m <sup xmlns:mml="http://www.w3.org/1998/Math/MathML"...
Abstract Radio-frequency (RF) driven helicon plasma sources can produce relatively high-density plasmas ( n > 10 19 m −3 ) at moderate powers (<2 kW) in argon. However, to similar for fusion relevant gases such as hydrogen (H), deuterium (D) and helium (He), much higher RF are needed. For very high powers, thermal issues of the RF-transparent dielectric window, used source design, limit operation timescales. To mitigate this constraint, we have designed, built tested a novel assembly...
The compact (R0~1.2-1.3m) Fusion Nuclear Science Facility (FNSF) is aimed at providing a fully integrated, continuously driven fusion nuclear environment of copious neutrons. This facility would be used to test, discover, and understand the complex challenges plasma material interactions, tritium fuel management, power extraction. Such properly designed provide, initially JET-level pressure (~30%T2) conditions (e.g., Hot-Ion H-Mode, Q<1)), an outboard neutron flux 0.25 MW/m2 while requiring...
The edge topology of magnetic fusion devices is decisive for the control plasma exhaust. In Wendelstein 7-X, island divertor concept will be used, which can change significantly as internal currents in a discharge evolve towards steady-state. Consequently, device has been optimized to minimize such currents, particular bootstrap current [1]. Nonetheless, there are predicted pulse scenarios where effects remaining could potentially lead overload plasma-facing components. These on long time...
The Prototype Material Plasma Exposure eXperiment (Proto-MPEX) is being used to qualify the plasma source and heating systems for (MPEX). MPEX will address important urgent research needs on material interactions future fusion reactors. In MPEX, plasma-facing components (nonirradiated a priori neutron irradiated) be exposed conditions as they are expected in steady-state device enabled by superconducting magnets, able break into new ground assessing materials at an ion fluence level range of...
The objective of Wendelstein 7-X is to demonstrate steady-state operation at β -values up 5%, ion temperatures several keV and plasma densities 2 × 1020 m−3. second operational phase foresees a fully high heat flux (HHF) divertor. Preparations are underway cope with residual bootstrap currents, either by electron cyclotron current drive or HHF protection elements. main heating system an resonance facility. Various technical improvements the gyrotrons have been implemented recently. They...
The Materials Plasma Exposure eXperiment (MPEX) is a linear plasma device that will address the plasma-material interaction (PMI) science for future fusion reactors and enable testing of plasma-facing components (PFCs). It designed as steady-state eventually delivering an ion fluence up to 10 <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">31</sup> m xmlns:xlink="http://www.w3.org/1999/xlink">-2</sup> target. be handle neutron-activated...
The Material Plasma Exposure eXperiment (MPEX) has completed its design phase. MPEX will be a unique facility to investigate plasma material interactions (PMIs) under fusion prototypic divertor conditions in steady state. This includes exposure expected reactor divertor. Materials investigated include solids, liquids, and neutron pre-irradiated materials. Electron ion heating allow for large operational domain ranging from erosion-dominated PMI deposition-dominated conditions. An overview of...
Plasma material interaction (PMI) studies are crucial to the successful development of future fusion reactors. Prototype Material Exposure eXperiment (Proto-MPEX) is a prototype design for MPEX, steady-state linear device being developed study PMI. The primary purpose Proto-MPEX developing plasma heating source concepts MPEX. A power accounting works identify machine operating parameters that could improve its performance, thereby increasing PMI research capabilities, potentially impacting...
The material's plasma exposure experiment (MPEX) is a steady-state, linear facility proposed to provide conditions that simulate the first wall and divertor of next-step fusion devices. MPEX will use an actively cooled, high-power helicon antenna as source. located outside vacuum region, during operation, significant percentage power deposited on facing surface window. window thus must be cooled so thermal stresses do not become excessive. design presented includes two cylindrical windows...
The Wendelstein 7-X stellarator experiment is scheduled for the completion of device commissioning and start first plasma in 2015.At two operational phases, inertially cooled test divertor unit will be replaced with an actively high heat-flux which enable to increase its pulse length steady-state performance.Plasma simulations show that evolution bootstrap current certain scenarios produce excessive heat fluxes on edge targets.It proposed place additional "scraper element" ten locations...
AbstractUnder the US Fusion Nuclear Science and Technology Development program, we have selected Dual Coolant Lead Lithium concept (DCLL) as a reference blanket, which has potential to be high performance DEMO blanket design with projected thermal efficiency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used structural material. The self-cooled breeder PbLi circulated for power conversion tritium breeding. A SiC-based flow channel insert (FCI) means magnetohydrodynamic...
The availability of future fusion devices such as a Fusion Nuclear Science Facility (FNSF) or DEMO greatly depends on long operating lifetimes plasma facing components in their divertors. ORNL is designing the Material-Plasma Exposure eXperiment (MPEX), superconducting magnet, steady-state device to address material interactions reactors. MPEX will utilize new high-intensity source concept based RF technology. This allow experiment cover entire expected conditions divertor reactor. It be...
Abstract NOTE: The first page of text has been automatically extracted and included below in lieu an abstract Session 2368 Multimedia Tutorials for Drawing Shear Force Bending Moment Diagrams Arnold Lumsdaine Department Mechanical Aerospace Bioengineering University Tennessee 414 Dougherty Engineering Building Knoxville, TN 37996 phone: (865) 974-6650 fax: 974-5274 alumsdai@engr.utk.edu Wilmorat Ratchukool Instructional Technology ABSTRACT Because multiple solution techniques, students...
An important step toward the advent of nuclear fusion as a future power source is development plasmafacing materials that can function designed for long period time. While ITER and other devices including Wendelstein 7-X Joint European Torus will provide insight into divertor first wall performance, dedicated device to advance understanding material performance in representative plasma environments needed. The Material Plasma Exposure eXperiment has been proposed linear generate direct...
The U.S. Fusion Energy Sciences Advisory Committee was charged "to identify the most promising transformative enabling capabilities (TEC) for to pursue that could promote efficient advance toward fusion energy, building on burning plasma science and technology." A subcommittee of technical experts formed received community input in form white papers presentations charge questions. identified four "most capabilities":1. advanced algorithms2. high critical temperature superconductors3....
The Wendelstein 7-X stellarator is in final stages of commissioning, and will begin operation late 2015. In the first phase, machine operate with a limiter, be restricted to low power short pulse. But 2019, plans are for an actively cooled divertor installed, steady state at full power. Recently, plasma simulations have indicated that, this operational bootstrap current evolve certain scenarios. This cause sensitive ends target overloaded beyond their qualified limit. A high heat flux...