Determination of Spatial and Spectral Distribution of Neutron Flux in the Texas A and M Nuclear Science Center Reactor Exposure Cell.

Abstract

Measurements were performed at the Nuclear Science Center to determine neutron flux distribution in the exposure cell. Both spatial and spectral flux variations were determined using neutron activation detectors. Results indicate hardening effects, and that 80%-90% of the total integral flux in the cell is due to neutrons having energies greater than 10 keV, indicating an intermediate spectrum. Results also indicate that the total integral flux increases near the concrete walls because of scattering. (Author)

Document Details

Document Type
Technical Report
Publication Date
Jun 01, 1976
Accession Number
ADA027825

Entities

People

  • J. A. Bachman
  • J. D. Randall
  • K. A. Hardy
  • R. F. Schumacher

Organizations

  • United States Air Force School of Aerospace Medicine

Tags

DTIC Thesaurus Topics

  • Concrete
  • Detectors
  • Diffraction
  • Hardening
  • Integrals
  • Measurement
  • Neutron Activation
  • Neutron Flux
  • Scattering
  • Spectra
  • Warning Systems

Fields of Study

  • Physics

Readers

  • Electrochemical Engineering/ Fuel Cell Technologies
  • Pulsed Power and Plasma Physics.
  • Spectroscopy.