The Energy Spectrum of Leakage Neutrons from a Homogeneous Reactor,

Abstract

The leakage neutron spectrum from a chain reaction in an aqueous solution of uranyl nitrate has been determined for the purpose of calibrating indium foil to be used for personnel monitoring of a possible accidental critical reaction at K-25. Approximately 75% of the neutrons were found to be slow, and experimental results are in reasonable agreement with a semi-theoretical treatment of the problem. The overall cross section of indium for neutrons of all energies in this leakage spectrum was found to be about 60 +/- 4 barns. This is of the same order of magnitude as the value of 126 barns which was determined from the calculated energy spectrum using weighted averages of directly measured cross sections.

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Document Details

Document Type
Technical Report
Publication Date
Jul 05, 1951
Accession Number
ADA297560

Entities

People

  • H. F. Henry
  • R. C. Rohr

Tags

Communities of Interest

  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Agreements
  • Aqueous Solutions
  • Chemical Reactions
  • Equations
  • Experimental Data
  • Fissile Materials
  • Fission Neutrons
  • Homogeneous Reactors
  • Measurement
  • Neutron Detectors
  • Neutron Flux
  • Neutron Spectrum
  • Neutrons
  • Nuclear Reactors
  • Thermal Neutrons
  • United States
  • Uranium Compounds

Fields of Study

  • Physics

Readers

  • Combustion science or combustion engineering.
  • Explosive Engineering.
  • Materials Science and Engineering.