D.L. Youchison

ORCID: 0000-0002-7366-1710
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About
Contact & Profiles
Research Areas
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Superconducting Materials and Applications
  • Magnetic confinement fusion research
  • Nuclear reactor physics and engineering
  • Nuclear Physics and Applications
  • Nuclear Engineering Thermal-Hydraulics
  • Advanced materials and composites
  • Spacecraft and Cryogenic Technologies
  • Heat Transfer and Boiling Studies
  • Graphite, nuclear technology, radiation studies
  • Metal and Thin Film Mechanics
  • Nuclear and radioactivity studies
  • Particle accelerators and beam dynamics
  • Heat and Mass Transfer in Porous Media
  • Diamond and Carbon-based Materials Research
  • Ion-surface interactions and analysis
  • Plasma Diagnostics and Applications
  • Ionosphere and magnetosphere dynamics
  • Semiconductor materials and devices
  • Metallurgical Processes and Thermodynamics
  • Engineering Applied Research
  • Additive Manufacturing and 3D Printing Technologies
  • Cold Fusion and Nuclear Reactions
  • Heat transfer and supercritical fluids

Oak Ridge National Laboratory
2016-2023

Government of the United States of America
2022

Sandia National Laboratories
2005-2015

Sandia National Laboratories California
2000-2014

Radiology Associates of Albuquerque
2010-2011

Intelligent Fusion Technology (United States)
2011

United States Department of Energy
2003-2007

Pennsylvania State University
1990-1995

United States Naval Research Laboratory
1991-1994

The technology to form and shoot high-Z cryogenic solid pellets mixed with deuterium using a gas gun that are shattered upon injection into plasma has been developed at Oak Ridge National Laboratory for mitigating disruptions. This selected as the basis baseline disruption mitigation system on ITER. development of pellet systems progressed be able accelerate large pure argon neon or without including deuterium. Impact studies have carried out shallow angles determine funnel performance in...

10.1088/1741-4326/ab136c article EN Nuclear Fusion 2019-03-26

A conclusive safety assessment of a fusion reactor requires that the thermal response divertor assembly is known with high degree accuracy. Such accuracy mandated because subjected to highest levels incident heat flux within reactor. In order accurately predict divertor's cooling channels, it necessary have complete model Nukiyama boiling curve for water conditions interest. Currently published models channels only included regimes forced convection, partially and fully developed nucleate...

10.13182/fst01-a11963345 article EN Fusion Technology 2001-03-01

Several commercial computational fluid dynamics (CFD) codes now have the capability to analyze Eulerian two-phase flow using Rohsenow nucleate boiling model. Analysis of due one-sided heating in plasma facing components (pfcs) is receiving attention during design water-cooled first wall panels for ITER that may encounter heat fluxes as high 5 MW/m2. Empirical thermalhydraulic correlations developed long fission reactor channels are not reliable when applied pfcs because fully conditions...

10.13182/fst11-a12348 article EN Fusion Science & Technology 2011-07-01

Plasma disruptions and edge localized modes can result in transient heat fluxes as high 5 MW/m <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">2</sup> on portions of a tokamak reactor first wall (FW). To accommodate these loads, the FW will likely use water-cooled hypervapotron heatsinks to enhance transfer. In this article, we present results computational fluid dynamics (CFD) study using 70 xmlns:xlink="http://www.w3.org/1999/xlink">°</sup> C...

10.1109/tps.2011.2180931 article EN IEEE Transactions on Plasma Science 2012-01-25

10.1016/j.fusengdes.2016.03.031 article EN Fusion Engineering and Design 2016-04-22

Within the ongoing U.S.-based program on development of liquid metal plasma-facing components, numerical simulations and analyses are performed to address feasibility open-surface Li divertor. In previous scoping studies (Smolentsev, 2021), heat-removal capabilities divertor were assessed using a simplified flow model for slug-type velocity profile constant thickness. Here, new take into account forces acting flowing layer. Three reduced-order mathematical models applied under conditions...

10.1109/tps.2022.3162141 article EN IEEE Transactions on Plasma Science 2022-04-22

Enhanced radial transport in the plasma and effect of ELMS may increase ITER first wall heat loads to as much 4 5 MW/m <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">2</sup> over localized areas. One proposed heatsink that can handle these higher is a CuCrZr hypervapotron. concept for panel consists 20 hypervapotron channels, each measuring 1400 mm long 48.5 wide. The nominal cooling conditions anticipated channel are 400 g/s water at 3 MPa...

10.1109/tps.2010.2049369 article EN IEEE Transactions on Plasma Science 2010-05-28

Plasma-spray technology is under investigation as a method for producing high thermal conductivity beryllium coatings use in magnetic fusion applications. Recent investigations have focused on optimizing the plasmaspray process depositing damaged surfaces. Of particular interest has been processing parameters to maximize through-thickness of coatings. Experimental results will be reported secondary H2 gas additions improve melting powder and negative transferred-arc cleaning bonding between...

10.1088/0031-8949/1996/t64/012 article EN Physica Scripta 1996-01-01

10.1016/j.nima.2011.06.010 article EN Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment 2011-06-26

A new class of helium-cooled high heat-flux plasma facing heat exchanger (HX) concept is presented. These unique "Foam-In-Tube" HX concepts are composed a thin tungsten shell integrally bonded to an open-cell foam core. High flux tests show maximum loads 22.4 MW/m2 using 4 MPa helium at flow rate 27 g/s. Based on these impressive performance results, and scalable channel with ultra-low pressure drop through the porous The primary advantage that media structure temperatures nearly independent...

10.13182/fst07-15 article EN Fusion Science & Technology 2007-10-01

Advances in high-performance computing now enable the engineering evaluation of large blanket components from a systems perspective at beginning normal design cycle. As an example, we discuss computational fluid dynamics (CFD) involved characterizing thermal performance entire 22.5 toroidal sector dual-coolant lead-lithium with particular attention to integrated manifolding and flow distributions. The inboard is roughly 7 m tall, has 321 first-wall helium-cooled channels, five parallel PbLi...

10.1080/15361055.2022.2123683 article EN Fusion Science & Technology 2022-12-21

Optical emission spectroscopy, Langmuir probes, and B-field probes have been used to characterize electron cyclotron resonance plasmas in the deposition of polycrystalline diamond films. These were generated at 1.33 Pa using selected ratios CO:H2 CH4:O2:H2 that produced highest quality films (i.e., high degree faceting an intense Raman peak 1332 cm−1). Electron temperature, ion density, plasma potential profiles obtained optimum growth conditions are presented. The best on silicon (100)...

10.1116/1.578275 article EN Journal of Vacuum Science & Technology A Vacuum Surfaces and Films 1993-01-01

AbstractHigh-heat-flux experiments on three types of helium-cooled divertor mock-ups were performed the 30-kW electron beam test system and its associated helium flow loop at Sandia National Laboratories. A dispersion-strengthened copper alloy (DSCu) was used in manufacture all mock-ups. The first heat exchanger manufactured by Creare, Inc., makes use microfin technology normal to heated surface. This provides for enhanced transfer relatively low rates much reduced pumping requirements....

10.13182/fst29-559 article EN Fusion Technology 1996-07-01
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