URANIUM--PLUTONIUM NITRIDE FUELS FOR LMFBR APPLICATIONS. Metadata

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Title

  • Main Title URANIUM--PLUTONIUM NITRIDE FUELS FOR LMFBR APPLICATIONS.

Publisher

  • Name: Battelle Memorial Institute
    Place of Publication: Columbus, Ohio
    Additional Info: Battelle Memorial Inst., Columbus, Ohio

Date

  • Creation: 1971-10-31

Language

  • English

Subject

  • Keyword: Fuels
  • Keyword: Ebr-2
  • Keyword: N30200* --Metals, Ceramics, & Other Materials--Ceramics & Cermets
  • Keyword: Fuel Pins
  • Keyword: Coolants
  • Keyword: Uranium Nitrides/Pun--Un, Fabrication Of Stainless Steel-Clad Irradiation Pellets Of, Methods For
  • Keyword: Testing
  • Keyword: Fabrication
  • Keyword: Bonding
  • Keyword: Compatibility
  • Keyword: N38700 --Reactor Components, Fuels & Accessories
  • Keyword: Diffusion
  • Keyword: Radiation Target Cans/Design And Fabrication For Use In Ebr-Ii And Treat
  • Keyword: High Temperature
  • Keyword: Radiation Effects
  • Keyword: Plutonium Nitrides/Pun--Un, Radiation Effects On Stainless Steel-Clad Pellets Of, Research Summary On Testing Of In-Pile
  • Keyword: Preparation
  • Keyword: Nitrogen/Determination In Sodium, Development Of Method For
  • Keyword: Reactors
  • Keyword: Uranium Nitrides/Pun--Un, Radioinduced Swelling Of Fuels Of, Deve
  • Keyword: Plutonium Nitrides
  • Keyword: Swelling
  • Keyword: Plutonium Nitrides/Pun--Un, Radioinduced Swelling Of Fuels Of, Development Of Model For
  • Keyword: Fuel Cans
  • Keyword: Experimental Breeder Reactor-Ii/Fuel Pins For, Data On Preparation Of Irradiation Test-Type
  • Keyword: Uranium Nitrides/Pun--Un, Radiation Effects On Stainless Steel-Clad Pellets Of, Research Summary On Testing Of In- Pile
  • Keyword: Reactor Fuels/Diffusion In Nitride, Methods For Determining Self-
  • Keyword: Pile Neutrons
  • Keyword: Sodium
  • Keyword: Lmfbr
  • Keyword: Thermodynamics
  • Keyword: Treat
  • Keyword: Reactor Fuel Elements/Bonding Of Nitride, To Cladding, Method For
  • Keyword: Uranium Nitrides Nitrogen/Determination In Sodium, Development Of Method For
  • Keyword: Sodium/ Analysis For Nitrogen, Development Of Method For
  • Keyword: Sodium/Use In Bonding Nitride Fuel Elements To Cladding, Development Of Method For

Source

  • Other Information: From Progress on development of fuels and technology for advanced reactors during July 1969--June 1970. 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.: BMI--1886
  • Grant Number: None
  • DOI: 10.2172/4089209
  • Office of Scientific & Technical Information Report Number: 4089209
  • Archival Resource Key: ark:/67531/metadc865996