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Title: EXPERIMENTAL INVESTIGATION OF FABRICATION OF Th--20 WT. PERCENT U FOR THE UMBR FUEL ELEMENT.

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Authors:: Copeland, G.L.; Queener, L.; Martin, W.R.

Publication Date:: Fri Jan 01 00:00:00 EST 1971

Research Org.:: Oak Ridge National Lab., Tenn.

OSTI Identifier:: 4738827

Report Number(s):: ORNL-TM-3499

NSA Number:: NSA-25-058185

DOE Contract Number:: W-7405-ENG-26

Resource Type:: Technical Report

Resource Relation:: Other Information: UNCL. Orig. Receipt Date: 31-DEC-71

Country of Publication:: United States

Language:: English

Subject:: N30120* -Metals, Ceramics, & Other Materials-Metals & Alloys-Preparation & Fabrication; N38700 -Reactor Components, Fuels & Accessories; BREEDER REACTORS; CASTING; ELECTRIC ARCS; FABRICATION; FUEL ELEMENTS; MELTING; THORIUM ALLOYS; URANIUM ALLOYS; REACTOR FUEL ELEMENTS/fabrication of hexagonal thorium- -uranium, for unclad metal breeder reactor; REACTORS, BREEDER/fuel elements for, fabrication of unclad metal; THORIUM ALLOYS AND SYSTEMS/Th-base-U, fabrication of fuel elements of, for unclad metal breeder reactor; URANIUM ALLOYS AND SYSTEMS/ Th-base-U, fabrication of fuel elements of, for unclad metal breeder reactor

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                    Copeland, G.L., Queener, L., and Martin, W.R. EXPERIMENTAL INVESTIGATION OF FABRICATION OF Th--20 WT. PERCENT U FOR THE UMBR FUEL ELEMENT..  United States: N. p., 1971. 
        Web.  doi:10.2172/4738827.

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                    Copeland, G.L., Queener, L., & Martin, W.R. EXPERIMENTAL INVESTIGATION OF FABRICATION OF Th--20 WT. PERCENT U FOR THE UMBR FUEL ELEMENT..  United States.  doi:10.2172/4738827.

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                    Copeland, G.L., Queener, L., and Martin, W.R. Fri .  
        "EXPERIMENTAL INVESTIGATION OF FABRICATION OF Th--20 WT. PERCENT U FOR THE UMBR FUEL ELEMENT.".  United States.  
        doi:10.2172/4738827.  https://www.osti.gov/servlets/purl/4738827.

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@article{osti_4738827,

  title        = {EXPERIMENTAL INVESTIGATION OF FABRICATION OF Th--20 WT. PERCENT U FOR THE UMBR FUEL ELEMENT.},

  author       = {Copeland, G.L. and Queener, L. and Martin, W.R.},

  abstractNote = {},

  doi          = {10.2172/4738827},

  journal      = {},

  number       = ,

  volume       = ,

  place        = {United States},

  year         = {Fri Jan 01 00:00:00 EST 1971},

  month        = {Fri Jan 01 00:00:00 EST 1971}

}

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Technical Report:

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DOI: 10.2172/4738827

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PROCESS DEVELOPMENT AND FABRICATION OF Th-7.6 WT % U FUEL ELEMENTS FOR THE SECOND CORE LOADING OF THE SODIUM REACTOR EXPERIMENT

Stanley, J.A. ; Binstock, M.H. September 1960

The second core loading for the Sodium Reactor Experiment (SRE), consisting of 45 seven-rcd fuel clusters, was fabricated. A process was developed to fabricate 0.750-in. diameter by 6.000-in. long slugs of Th--7.6 wt.% U alloy. The NaK bending of slugs to stainless-steel cladding was successfully accomplished. (auth)
VANADIUM ALLOY SCREENING STUDIES AND FABRICATION OF V--15 WT. PERCENT Ti-- 7.5 WT. PERCENT Cr TUBING FOR NUCLEAR FUEL CLADDING.

Kramer, W.C. ; Burt, W.R. Jr. ; Karasek, F.J. ; ... January 1966
DOI: 10.2172/4450104

Full Text Available
BEHAVIOR OF Th--20 WT PERCENT U FAST-REACTOR FUEL UNDER TRANSIENT HEATING TO FAILURE.

Dickerman, C.E. ; Robinson, L.E. ; Blumenthal, B. ; ... January 1967 - Nucl. Appl., 3: 9-17(Jan. 1967).
EFFECT OF CHLORIDE IONS ON THE SUSCEPTABILITY TO STRESS CORROSION CRACKING OF U-7$sup 1$/$sub 2$ WT PERCENT Nb-2$sup 1$/$sub 2$ WT PERCENT Zr AND U-4$sup 1$/$sub 2$ WT PERCENT Nb ALLOYS.

Magnani, N.J. ; Romero, H. ; Miglionico, C.J. January 1970
REACTION OF WATER VAPOR WITH U--7$sup 1$/$sub 2$ WT. PERCENT Nb--2$sup 1$/ $sub 2$ WT. PERCENT Zr AND U--4$sup 1$/$sub 2$ WT. PERCENT Nb.

Magnani, N.J. ; Romero, H. January 1972