THE EFFECT OF NUCLEAR RADIATION ON DISPERSION FUEL MATERIALS

Abstract

A complete summary of the irradiation performance of the various fuel materials dispersed in different matrices has been collected. The irradiation performance of the following dispersions is discussed in the report: BeO-UO2, BeO-UO2-ThO2, Al2O3-UO2, MgO-UO2, UO2, UC, UC2, and *U, Th)C2 U3O8 glass, and UAl3 dispersed in aluminum; UO2, UC, and UN dispersed in stainless steel; UO2 and UO2-Y2O3 dispersed in nickel-chromium alloys; UO2 dispersed in niobium, UO2 dispersed in molybdenum, UO2, UN, and UC dispersed in tungsten. The data which is summarized includes percentage of fuel by weight and volume, specimen shape and size, fuel particle size, cladding material and clad thickness, irradiation temperature, heat generation rates, irradiation times, fuel burnup, fission gas release, dimensional and density changes resulting from irradiation.

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Document Details

Document Type
Technical Report
Publication Date
Jan 01, 1966
Accession Number
AD0484683

Entities

People

  • M. Kangilaski

Organizations

  • Battelle Memorial Institute

Tags

Communities of Interest

  • Advanced Electronics
  • Air Platforms
  • Counter WMD
  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Aluminum Oxides
  • Ceramic Materials
  • Chemistry
  • Chromium
  • Chromium Alloys
  • Crystal Structure
  • Fast Neutrons
  • Materials
  • Materials Laboratories
  • Materials Processing
  • Materials Science
  • Materials Testing
  • Nuclear Fuels
  • Nuclear Radiation
  • Refractory Metals
  • Tensile Strength
  • X-Ray Diffraction

Fields of Study

  • Physics

Readers

  • Aerosol Science/Aerosol Physics
  • Research Science/Academic Research
  • Thin Film Deposition Science.