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

الملخص EN

The MCNP5-beta code was used in this research to calculate the neutron fluxes for the neutron sources Ra-Be, Am-Be and Cf which produced in the irradiation channels of the Paraffin neutron irradiator.

The calculated results show that the total neutron flux values in all of the irradiated channels are higher for the Am-Be neutron source than those obtained for the Ra-Be, Cf neutron sources, and the ratio of the thermal neutron flux of the Cf neutron source is higher (magnitude about 82%) than that obtained for the Ra-Be and Am-Be neutron source (magnitude about 75% and 71.7% respectively).