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Monday, May 11, 2020 | History

3 edition of Creep behavior of tungsten/niobium and tungsten/niobium-1 percent zirconium composites found in the catalog.

Creep behavior of tungsten/niobium and tungsten/niobium-1 percent zirconium composites

Creep behavior of tungsten/niobium and tungsten/niobium-1 percent zirconium composites

  • 165 Want to read
  • 16 Currently reading

Published by U.S. Dept. of Energy, Nuclear Energy, Reactor Systems Development and Technology, For sale by the National Technical Information Service in Washington, DC, [Springfield, Va .
Written in English

    Subjects:
  • Composite materials.,
  • Materials -- Creep.

  • Edition Notes

    StatementDonald W. Petrasek and Robert H. Titran.
    SeriesNASA TM -- 100804, NASA technical memorandum -- 100804..
    ContributionsTitran, Robert H., United States. Office of the Assistant Secretary for Nuclear Energy. Deputy Assistant Secretary for Reactor Systems Development and Technology., United States. National Aeronautics and Space Administration.
    The Physical Object
    FormatMicroform
    Pagination1 v.
    ID Numbers
    Open LibraryOL17099557M


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Creep behavior of tungsten/niobium and tungsten/niobium-1 percent zirconium composites Download PDF EPUB FB2

Get this from a library. Creep behavior of tungsten/niobium and tungsten/niobium-1 percent zirconium composites. [Donald W Petrasek; Robert H Titran; United States. Office of the Assistant Secretary for Nuclear Energy.

Deputy Assistant Secretary for Reactor Systems Development and Technology.; United States. National Aeronautics and Space Administration.].

Conference: Creep behavior of tungsten/niobium and tungsten/niobium-1 percent zirconium composites. Creep behavior of tungsten/niobium and tungsten/niobium-1 percent zirconium composites. Full Record. Conference: Creep behavior of tungsten fiber reinforced niobium metal matrix composites.

Creep behavior of tungsten/niobium and tungsten/niobium-1 percent zirconium composites [microform] / Donald W. Petrasek and Robert H. Titran U.S. Dept. of Energy, Nuclear Energy, Reactor Systems Development and Technology ; For sale by the National Technical Information Service Washington, DC: [Springfield, Va Australian/Harvard Citation.

Buy Creep behavior of tungsten/niobium and tungsten/niobium-1 percent zirconium composites (SuDoc NAS ) by Donald W. Petrasek (ISBN:) from Amazon's Book Store. Everyday low prices and free delivery on eligible : Donald W.

Petrasek. The creep behavior and microstructural stab niobium and niobium-1% zirconium was determ lity of tungsten ned at and creep equation. A linear relationship was found to exist creep rate of the composite and the inverse of the compos life.

achieve 1 percent creep strain and in rupture strength at The composite materials had an order of. Request PDF | Effect of fiber volume fraction on the fracture behavior of Nb-1 Wt Pct Zr/W composites at elevated temperatures | Nb-1 wt pct Zr/W.

D.W. Petrasek and R.H. Titran: “Creep Behavior of Tungsten/Niobium and Tungsten/Niobium-1 Percent Zirconium Composites,” NASA TM, NASA-Lewis Research Center, Cleveland, OH, Google ScholarAuthor: S.

Raj, L. Ghosn. Compression creep of filamentary composites [microform] / by D.L. Graesser, M.E. Tuttle National Aeronautics and Space Administration [Washington, DC Australian/Harvard Citation. Graesser, Douglas Lee. & Tuttle, M. & United States. National Aeronautics and. Effect of Fiber Volume Fraction on the Fracture Behavior of Nb-1 Wt Pct Zr/W Composites at Elevated Temperatures S.V.

RAJ and L.J. GHOSN Nb-1 wt pct Zr/W long-fiber composite monotapes, nominally containing 0 to 70 vol pct of tungsten fibers, were fabricated by arc spraying the Nb-1 pct Zr matrix onto the tungsten fibers. This banner text can have markup. web; books; video; audio; software; images; Toggle navigation.

Search ; Patent registration. Method of coating graphite tubes with refractory metal carbides. DOEpatents. Wohlberg, C. A method of coating graphite tubes with a refractory metal carbide is.

FUEL ELEMENT. DOEpatents. Bean, R.W. A ceramic fuel element for a nuclear reactor that has improved structural stability as .