Rhodium-103 and Indium-115 Inelastic Scattering Reactions for Fission Neutron Dosimetry.

Abstract

Neutron activation foil cross sections are calculated for shielded and unshielded configurations of the AFRRI TRIGA reactor. The neutron spectra used in the calculations ranged in average energy from 0.55 MeV to 3.4 MeV, and the total range of activation foil sensitivity factors (cross section per unit tissue-kerma) was + or - 8.5% for 103Rh (n,n') 13mRh, + or - 20% for 115In (n,n') 115mIn, and + or - 75% for 32S (n,p)32P. These results support the use of 103 Rh and 115 In activation foils as tissue-kerma dosimeters at the AFRRI TRIGA reactor. (Author)

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Document Details

Document Type
Technical Report
Publication Date
Dec 01, 1984
Accession Number
ADA155188

Entities

People

  • G. H. Zeman

Organizations

  • Armed Forces Radiobiology Research Institute

Tags

Communities of Interest

  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Accuracy
  • Detectors
  • Dosimetry
  • Energy
  • Fission Neutrons
  • Inelastic Scattering
  • Ionization Chambers
  • Measurement
  • Neutron Scattering
  • Neutron Spectrum
  • Neutrons
  • Physical Activity
  • Radiation
  • Radiobiology
  • Scattering
  • Spectra
  • Thermal Neutrons

Fields of Study

  • Physics

Readers

  • Nuclear and Radiation Engineering.
  • Solar Physics