Purpose of this paper is to present shielding analyses that will be performed using the 3-D discrete ordinates code TORT and Monte Carlo code MCNP to assess neutron and gamma flux and dose distribution within the IRIS reactor vessel, containment, and extending beyond the containment outer boundary.

Evaluation of Radiation Field in the IRIS Nuclear Power Plant Using 3-D Transport Theory Analysis

PADOVANI, ENRICO;CAMMI, ANTONIO
2008

Abstract

Purpose of this paper is to present shielding analyses that will be performed using the 3-D discrete ordinates code TORT and Monte Carlo code MCNP to assess neutron and gamma flux and dose distribution within the IRIS reactor vessel, containment, and extending beyond the containment outer boundary.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11311/562613
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