Title of article
Determination of neutron flux distribution in an Am–Be irradiator using the MCNP
Author/Authors
K. Shtejer-Diaz، نويسنده , , C. B. Zamboni، نويسنده , , G. S. Zahn، نويسنده , , J. Y. Zevallos-Ch?vez، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2003
Pages
4
From page
263
To page
266
Abstract
A neutron irradiator has been assembled at IPEN facilities to perform qualitative–quantitative analysis of many materials using thermal and fast neutrons outside the nuclear reactor premises. To establish the prototype specifications, the neutron flux distribution and the absorbed dose rates were calculated using the MCNP computer code. These theoretical predictions then allow one to discuss the optimum irradiator design and its performance.
Keywords
MCNP , Neutron flux , neutron dose
Journal title
Applied Radiation and Isotopes
Serial Year
2003
Journal title
Applied Radiation and Isotopes
Record number
541530
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