حساب الجرعة الإشعاعية للمصادر النترونية Cf252، Am-Be241، Ra-be226 باستعمال الكود MCNP5-beta

Abstract EN

The general-purpose Monte Carlo modeling code MCNP5-beta was used in this research for calculating the radiation dose produced from Am-Be, Ra-Be and Cf neutron sources at the surface of a paraffin neutron irradiator.

The calculation results show that: 1.

The neutron flux at the surface of the irradiator for the Am-Be source is larger than for the Ra-Be or Cf sources, with ratios 48.82% and 95.33% respectively.

2.

The average radiation dose at the surface of the irradiator from the Am-Be neutron source is larger than for the Ra-Be or Cf sources, by 14.79% and 36.65% respectively.

3.

The neutron and photon dose ratios at the surface of the irradiator are 77.34% and 22.66% for the RaBe source, 84.60% and 24.17% for the Am-Be source, and 56.11% and 43.89% for the Cf source.

Finally it was concluded that the Cf source is better for use in the paraffin neutron irradiator, because the dose at the surface of irradiator is the lowest compared with the Am-Be and Ra-Be sources.