Title: Automatic modelling of complex geometries for MCNP simulation using GEOMIT code

Authors: Noha Shaaban; Wael El Gammal; Hesham Nasif; Hidetsugu Morota

Addresses: The Egyptian Nuclear and Radiological Regulatory Authority, Nasr City, P.O. Box 11762, Cairo, Egypt ' The Egyptian Nuclear and Radiological Regulatory Authority, Nasr City, P.O. Box 11762, Cairo, Egypt ' MHI Nuclear Engineering Co. Ltd., Yokohama, 220-8401, Japan ' MHI Nuclear Engineering Co. Ltd., Yokohama, 220-8401, Japan

Abstract: The need for an automatic CAD/MCNP conversion interface appeared due to the complexity of the geometries and the difficulty to transfer their models to the MCNP input manually. GEOMIT is a code that has been developed to automatically generate MCNP surface and cell cards with the capability to produce solid and void cells in a simple geometry without using union or complement operators. This work shows the success of the code for modelling different test cases for the active well coincidence counter geometry which is of great importance for nuclear safeguard applications. Also, a great improvement in calculation time was obtained compared to the manual geometry calculations due to explicit void creation.

Keywords: MCNP-CAD interface; GEOMIT; solid geometry; visualisation; complex geometries; MCNP simulation; Monte Carlo N-Particle; Monte Carlo simulation; nuclear safety; mathematical modelling; active-well neutron coincidence counter; AWCC; nuclear energy; nuclear power.

DOI: 10.1504/IJESMS.2015.070106

International Journal of Engineering Systems Modelling and Simulation, 2015 Vol.7 No.3, pp.158 - 165

Received: 31 Aug 2012
Accepted: 28 Sep 2013

Published online: 21 Mar 2015 *

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