High heat flux testing capabilities at Sandia National Laboratories - New Mexico Metadata

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Title

  • Main Title High heat flux testing capabilities at Sandia National Laboratories - New Mexico

Creator

  • Author: Youchison, D.L.
    Creator Type: Personal
  • Author: McDonald, J.M.
    Creator Type: Personal
  • Author: Wold, L.S.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE, Washington, DC (United States)

Publisher

  • Name: Sandia National Laboratories
    Place of Publication: Albuquerque, New Mexico
    Additional Info: Sandia National Labs., Albuquerque, NM (United States)

Date

  • Creation: 1994-12-31

Language

  • English

Description

  • Content Description: High heat flux testing for the United States fusion power program is the primary mission of the Plasma Materials Test Facility (PMTF) located at Sandia National Laboratories - New Mexico. This facility, which is owned by the United States Department of Energy, has been in operation for over 17 years and has provided much of the high heat flux data used in the design and evaluation of plasma facing components for many of the world`s magnetic fusion, tokamak experiments. In addition to domestic tokamaks such as Tokamak Fusion Test Reactor (TFTR) at Princeton and the DIII-D tokamak at General Atomics, components for international experiments like TEXTOR, Tore-Supra, and JET also have been tested at the PMTF. High heat flux testing spans a wide spectrum including thermal shock tests on passively cooled materials, thermal response and thermal fatigue tests on actively cooled components, critical heat flux-burnout tests, braze reliability tests and safety related tests. The objective of this article is to provide a brief overview of the high heat flux testing capabilities at the PMTF and describe a few of the experiments performed over the last year.
  • Physical Description: 8 p.

Subject

  • Keyword: Heat Flux
  • Keyword: Nondestructive Testing
  • STI Subject Categories: 70 Plasma Physics And Fusion
  • Keyword: Thermal Testing
  • Keyword: Thermal Fatigue
  • Keyword: Thermonuclear Reactor Materials
  • Keyword: Tokamak Devices
  • Keyword: Test Facilities

Source

  • Conference: American Society of Mechanical Engineers` winter annual meeting, Chicago, IL (United States), 6-11 Nov 1994

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • Other: DE96001942
  • Report No.: SAND--95-2331C
  • Report No.: CONF-941142--36
  • Grant Number: AC04-94AL85000
  • Office of Scientific & Technical Information Report Number: 123255
  • Archival Resource Key: ark:/67531/metadc622331

Note

  • Display Note: OSTI as DE96001942