RECOVERY OF PLUTONIUM AND URANIUM FROM REACTOR FUEL METALLURGICAL SCRAP Metadata

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Title

  • Main Title RECOVERY OF PLUTONIUM AND URANIUM FROM REACTOR FUEL METALLURGICAL SCRAP

Creator

  • Author: Schulz, W.W.
    Creator Type: Personal

Contributor

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

Publisher

  • Name: Pacific Northwest Laboratory
    Place of Publication: Richland, Washington
    Additional Info: Battelle-Northwest, Richland, Wash. Pacific Northwest Lab.

Date

  • Creation: 1965-06-01

Language

  • English

Description

  • Physical Description: Pages: 30

Subject

  • Keyword: Tables
  • Keyword: Fuels
  • Keyword: Thorium
  • Keyword: Chemistry
  • Keyword: Quantity Ratio
  • Keyword: Equations
  • Keyword: Separation Processes
  • Keyword: Residues
  • Keyword: Nitric Acid
  • Keyword: Separation Processes And Procedures
  • Keyword: Uranium
  • Keyword: Carbon Tetrachloride
  • Keyword: Solvent Extraction
  • Keyword: Butyl Phosphates
  • Keyword: Distribution
  • Keyword: Plutonium
  • Keyword: Numericals
  • Keyword: Diagrams

Source

  • Other Information: Orig. Receipt Date: 31-DEC-65

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.: BNWL-57
  • Grant Number: AT(45-1)-1830
  • Office of Scientific & Technical Information Report Number: 4576739
  • Archival Resource Key: ark:/67531/metadc1028997

Note

  • Display Note: NTIS