INVESTIGATION OF THE CRITICAL HEAT FLUX FOR TUBULAR FUEL ELEMENTS OF AN ATOMIC POWER PLANT,

Abstract

The results of investigating the boiling crisis during the flow of subcooled water and a steam-water mixture in tubes are given. The validity of using data obtained on tubes for calculating the critical heat flux in the tubular fuel elements of nuclear reactors is substantiated. (Author)

Document Details

Document Type
Technical Report
Publication Date
Apr 07, 1965
Accession Number
AD0614769

Entities

People

  • O. L. Peskov
  • V. A. Zenkevich
  • V. I. Subbotin

Organizations

  • National Air and Space Intelligence Center

Tags

DTIC Thesaurus Topics

  • Electric Generators
  • Electric Power Plants
  • Energy Systems
  • Heat Flux
  • Nuclear Power Plants
  • Nuclear Reactors

Fields of Study

  • Physics

Readers

  • Combustion and Flow Dynamics.
  • Nuclear Non-Proliferation and International Security