ERSN-OpenMC, a Java-based GUI for OpenMC Monte Carlo code

Publication date: Available online 21 December 2015 Source:Journal of Radiation Research and Applied Sciences Author(s): Jaafar EL Bakkali, Tarek EL Bardouni, Seyedmostafa Safavi, Hamid Boukhal, Mohamed Kaddour, Khalid Benaalilou, Essaid Chham OpenMC is a new Monte Carlo transport particle simulation code focused on solving two types of neutronic problems mainly the k-eigenvalue criticality fission source problems and external fixed fission source problems. OpenMC does not have any Graphical User Interface and the creation of one is provided by our java-based application named ERSN-OpenMC. The main feature of this application is to provide to the users an easy-to-use and flexible graphical interface to build better and faster simulations, with less effort and great reliability. Additionally, this graphical tool was developed with several features, as the ability to automate the building process of OpenMC code and related libraries as well as the users are given the freedom to customize their installation of this Monte Carlo code. A full description of the ERSN-OpenMC application is presented in this paper.
Source: Journal of Radiation Research and Applied Sciences - Category: Physics Source Type: research