Averaged U238 Fission Cross Section Measurement in Cf-252 Neutron Spectrum

  • A. Pazirandeh
  • Y. Ahmedi-zadeh
Conference paper
Part of the Research Reports in Physics book series (RESREPORTS)


With regard to the standardization of Cf-252 neutron spectrum, the averaged U-238 fission cross section was measured over the Cf-252 neutron spectrum using foil activation technique. The gamma spectra of the fission products were obtained on a pure germanium detector at different decay times in order to identify the gamma rays of short, medium and long half-life radioisotopes. Analyzing the gamma spectra of the irradiated uranium foils several distinct photopeaks of several fission products were identified. The pure activity of Te-132 was determined from the net area under 228.2 kev photopeak after correcting it for neighbouring photopeaks of Np-239 and Pa-234. The averaged U238 fission cross section was calculated from the corrected counts of Te-132 photopeak to be 329 ± 10mb. The main sources of errors in the measurements are mainly due to inaccuracy of location of foils, neutron flux, counting statistics, weight of foils, impurity of foils and interferences from neighbouring photopeaks. The contribution of fission, neutrons from spontaneous fission of Cm-248, daughter of Cf-252, to the total flux density was estimated at 0.13 %.


Neutron Flux Fission Product Spontaneous Fission Gamma Spectrum Fission Neutron Spectrum 
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Copyright information

© Springer-Verlag Berlin Heidelberg 1992

Authors and Affiliations

  • A. Pazirandeh
    • 1
    • 2
  • Y. Ahmedi-zadeh
    • 1
    • 2
  1. 1.Physics DepartmentTeheran UniversityTeheranIran
  2. 2.Nuclear Research Center, AEOIIran

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