HIGH TEMPERATURE PROPERTY STUDY FOR REENTERING NAP SYSTEMS.

Abstract

The experimental determination of the properties of hydrided zirconium-uranium alloy is part of a larger program entitled ''Nuclear Auxiliary Power System Re-entry and Disposal Phenomena.'' The following properties were determined over the temperature range from room temperature to 3260 degrees R: linear thermal expansion, thermal conductivity, specific heat, heat of fusion, heat of combustion, total normal emissivity, tensile strength, rate of hydrogen loss, rate of oxida tion, and loss of fuel integrity at high heat flux. Rate of oxidation studies showed that when a hydrided zirconium-uranium alloy specimen was exposed to a temperature of 3010 degrees R in a furnace containing an air atmosphere, the speci men developed large fissures and brke into sev eral smaller pieces. However, an actual hydrided zirconium-uranium fuel element rod exposed to a somewhat higher heat flux in an inert atmosphere developed several large cracks but did not break into smaller pieces. (Author)

Document Details

Document Type
Technical Report
Publication Date
Jun 01, 1963
Accession Number
AD0412586

Entities

People

  • E. Howe
  • J.c. Hedge
  • J.i. Lang
  • Robert J. Elliott

Organizations

  • IIT Research Institute

Tags

DTIC Thesaurus Topics

  • Alloys
  • Atmospheres
  • Controlled Atmospheres
  • Elements
  • Heat Energy
  • Heat Flux
  • Heat Of Combustion
  • Heat Of Fusion
  • High Temperature
  • Specific Heat
  • Tensile Strength
  • Thermal Conductivity
  • Thermal Expansion
  • Uranium
  • Uranium Alloys
  • Zirconium

Readers

  • Combustion science or combustion engineering.
  • Materials Science (Mechanical Engineering).
  • Materials Science and Engineering.