Fast Reactor Mixed-Carbide Fuel Element Development Program. Twelfth Quarterly Progress Report, April--June 1970. Metadata

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Title

  • Main Title Fast Reactor Mixed-Carbide Fuel Element Development Program. Twelfth Quarterly Progress Report, April--June 1970.

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization

Publisher

  • Name: United Nuclear Corp., Elmsford, N. Y. Research and Engineering Center
    Place of Publication: United States

Date

  • Creation: 1970-01-01

Language

  • English

Description

  • Physical Description: 32 p.

Subject

  • Keyword: Reactor Fuel Elements/ Performance Of Carbide, In Treat
  • Keyword: Plutonium Carbides/Puc--Uc, Radiation Effects On Stainless Steel-Clad Fuel Pellets Of, In-Pile
  • Keyword: Plutonium Carbides/Puc--Uc, Radiation Effects On Sodium-Bonded Clad Fuels Of, In-Pile
  • Keyword: Pellets Density-- Ebr-2-- Irradiation-- Plutonium Oxides-- Powders-- Pressure-- Radiation Effects-- Testing-- Uranium Oxides Uranium Carbides/Puc--Uc, Radiation Effects On Stainless Steel-Clad Fuel Pellets Of, In-Pile
  • Keyword: Uranium Carbides/Puc-- Uc, Radiation Effects On Sodium-Bonded Clad Fuels Of, In-Pile
  • Keyword: N30250* --Metals, Ceramics, & Other Materials--Ceramics & Cermets--Radiation Effects
  • Keyword: Reactor Fuel Elements/Radiation Effects On Rod-Type Carbide, At 70 To 35 Kw/Ft, In-Pile
  • Keyword: Reactor Fuel Elements/Radiation Effects On Fission Gas Release And Swelling Of Unrestrained Carbide, In-Pile
  • Keyword: Plutonium Carbides/Puc--Uc, Radiation Effects On Incoloy 800-Clad Fuel Pellets Of, In-Pile
  • Keyword: Uranium Carbides/Puc--Uc, Radiation Effects On Incoloy 800-Clad Fuel Pellets Of, In-Pile
  • Keyword: Plutonium Oxides Puo$Sub 2$/Puo$Sub 2$--Uo$Sub 2$, Fabrication Of Pellets Of, For Ebr-Ii Irradiation
  • Keyword: N38150 --Power Reactor Development--Fuels
  • Keyword: Fabrication
  • Keyword: Uranium Oxides Uo$Sub 2$/Puo$Sub 2$--Uo$Sub 2$, Fabrication Of Pellets Of, For Ebr-Ii Irradiation
  • Keyword: Ebr-2-- Fission Products-- Fuel Cans-- Fuels-- Gases-- Incoloy-- Irradiation-- Plutonium Carbides-- Power-- Production-- Radiation Effects-- Rods-- Stainless Steel-304-- Stainless Steel-316-- Swelling-- Testing-- Treat-- Uranium Carbides-- Voids
  • Keyword: Uranium Carbides/Puc--Uc, Radiation Effects On Stainless Steel-Clad Fuel Pellets Of, In-Pile

Source

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

Collection

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

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Report No.: UNC--5263
  • Grant Number: AT(30-1)-3415
  • DOI: 10.2172/4097063
  • Office of Scientific & Technical Information Report Number: 4097063
  • Archival Resource Key: ark:/67531/metadc868188

Note

  • Display Note: Dep. NTIS.
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