Shielding design studies for a neutron irradiator system based on a 252Cf source.

A X da Silva; V R Crispim

doi:10.1093/oxfordjournals.rpd.a006557

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Shielding design studies for a neutron irradiator system based on a 252Cf source.

A X da Silva·V R Crispim

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Abstract

This study aims to investigate a shielding design against neutrons and gamma rays from a source of 252Cf, using Monte Carlo simulation. The shielding materials studied were borated polyethylene, borated-lead polyethylene and stainless steel. The Monte Carlo code MCNP4B was used to design shielding for 252Cf based neutron irradiator systems. By normalising the dose equivalent rate values presented to the neutron production rate of the source, the resulting calculations are independent of the intensity of the actual 252Cf source. The results show that the total dose equivalent rates were reduced significantly by the shielding system optimisation.

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Boron Neutron Capture Therapy Californium Gamma Rays Humans Monte Carlo Method Neutron Activation Analysis Neutrons Polyethylene Radiation Dosage Radiation Protection Radiobiology Radiometry Journal Article Research Support, Non-U.S. Gov't

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A X da Silva, V R Crispim. 2001. Shielding design studies for a neutron irradiator system based on a 252Cf source.. https://doi.org/10.1093/oxfordjournals.rpd.a006557

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