THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME

Title: THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME

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Abstract

A body is presented for use in a thermal fission reactor comprising a sintered compressed mass of a substance of the group consisting of uranium, thorium, and oxides and carbides of uranium and thorium, enclosed in an envelope of a sintered, compacted, heat-conductive material of the group consisting of beryllium, zirconium, and oxides and carbides of beryllium and zirconium.

Inventors:: Blainey, A.

Issue Date:: 1959-10-01

Research Org.:: Originating Research Org. not identified

OSTI Identifier:: 4192511

Patent Number(s):: 2907705

Assignee:: U.S. Atomic Energy Commission DTIE; NSA-14-008261

NSA Number:: NSA-14-008261

Resource Type:: Patent

Resource Relation:: Other Information: Orig. Receipt Date: 31-DEC-60

Country of Publication:: United States

Language:: English

Subject:: REACTOR TECHNOLOGY; BERYLLIUM; BERYLLIUM CARBIDES; BERYLLIUM OXIDES; FUEL ELEMENTS; HEAT TRANSFER; REACTORS; SINTERED MATERIALS; THERMAL CONDUCTIVITY; THORIUM; THORIUM CARBIDES; THORIUM OXIDES; URANIUM; URANIUM CARBIDES; URANIUM OXIDES; ZIRCONIUM; ZIRCONIUM CARBIDES; ZIRCONIUM OXIDES

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                    Blainey, A. THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME.  United States: N. p., 1959. 
        Web.

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                    Blainey, A. THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME.  United States.

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                    Blainey, A. Thu .  
        "THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME".  United States.

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@article{osti_4192511,

  title        = {THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME},

  author       = {Blainey, A.},

  abstractNote = {A body is presented for use in a thermal fission reactor comprising a sintered compressed mass of a substance of the group consisting of uranium, thorium, and oxides and carbides of uranium and thorium, enclosed in an envelope of a sintered, compacted, heat-conductive material of the group consisting of beryllium, zirconium, and oxides and carbides of beryllium and zirconium.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1959},

  month        = {10}

}

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