Naslov
Software Development for Visualization of Monte Carlo Results Based on the MCNP Program

Autori
Matijević, Mario ; Markota, Domagoj ; Grgić, Davor

Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), znanstveni

Izvornik
Proceedings of the International Conference Nuclear Energy for New Europe 2019 / Smodiš, Borut ; Udir, Nina - Ljubljana : Nuclear Society of Slovenia, 2019

ISBN
978-961-6207-47-8

Skup
International Conference Nuclear Energy For New Europe (NENE)

Mjesto i datum
Portorož, Slovenija, 09.09.2019. - 12.09.2019

Vrsta sudjelovanja
Poster

Vrsta recenzije
Međunarodna recenzija

Ključne riječi
MCNP, MTV3D, graphical user interface, mesh tally

Sažetak
MCNP is a well known and widely used computer code for general purpose Monte Carlo transport simulation of neutrons, photons and electrons through arbitrary three-dimensional configurations. Important feature of the code is a graphical display of the model geometry using X Server for Windows, which is useful for geometry checking during input preparation. Another important graphical feature of MCNP is ability to display Monte Carlo results and associated uncertainties from a mesh-based tally file (i.e. meshtal file) over a structured XYZ mesh. Such results are quite important to the user, since they give an overall insight of Monte Carlo convergence process in a phase-space and effectiveness of the selected variance reduction parameters. Even though routines for basic mesh tally plotting are useful (say Xming), there is still a space left for improvement of such mesh-based visualization process. This paper presents such an attempt with development of MTV3D tool with a graphical user interface for visualization of the MCNP meshtal file. Basic features and functionality of MTV3D are presented for selected real-life shielding problems, such as Ueki shielding benchmark and PWR cask dose rates.

Izvorni jezik
Engleski

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