The Average Fission Cross Section of U233, U234, and U236 in the Fast Reactor Neutron Spectrum,

Abstract

The report to follow gives results of a series of fission cross section measurements in the high energy neutron spectrum of the fast reactor.

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Document Details

Document Type
Technical Report
Publication Date
May 18, 1951
Accession Number
ADA297583

Entities

People

  • E. Jurney

Organizations

  • Los Alamos National Laboratory

Tags

Communities of Interest

  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Classified Materials
  • Energy
  • Fast Neutrons
  • Fast Reactors
  • Fission
  • Fissionable Materials
  • High Energy
  • Materials
  • Measurement
  • Neutron Cross Sections
  • Neutron Spectrum
  • Neutrons
  • New Mexico
  • Nuclear Energy
  • Spectra
  • United States

Fields of Study

  • Physics

Readers

  • Business Analytics
  • Nuclear and Radiation Engineering.