Published January 1997 | Version v1
Miscellaneous Open

Installation and validation of MCNP-4A

Description

MCNP-4A is a multi-purpose Monte Carlo program suitable for the modelling of neutron, photon, and electron transport problems. It is a particularly useful technique when studying systems containing irregular shapes. MCNP has been developed over the last 25 years by Los Alamos, and is distributed internationally via RSIC at Oak Ridge. This document describes the installation of MCNP-4A (henceforth referred to as MCNP) on the Silicon Graphics workstation (bluey.ansto.gov.au). A limited number of benchmarks pertaining to fast and thermal systems were performed to check the installation and validate the code. The results are compared to deterministic calculations performed using the AUS neutronics code system developed at ANSTO. (author)

Availability note (English)

Available from INIS in electronic form

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Additional details

Publishing Information

Imprint Pagination
16 p.
Report number
NTD-TN--200