Proceedings of the 2011 International Conference on Informatics, Cybernetics, and Computer Engineering (ICCE2011) November 19–20, 2011, Melbourne, Australia pp 125-131 | Cite as
Interactive Visualization of MCNP-Based Neutronics Models
Abstract
MCNP is a general-purpose Monte Carlo N-Particle code that is widely used in many fields such as radiation protection, dosimetry, radiation shielding, radiography, medical physics, nuclear criticality safety, etc. It can treat an arbitrary three-dimensional configuration of materials in geometric cells. However, it is difficult and time-consuming to visualize and verify the MCNP input file. In order to conveniently check and analyze the MCNP input file, with the development of computer technology, on the basis of mature geometry engine, OOP (Object-Oriented Programming) technique, FDS Team implemented interactive visualization system converting geometry description of MCNP input file into 3D CAD models, which can facilitate to check and analyze the input file. Furthermore, the CAD models generating from the input file can be imported into other commercial CAD software for editing, updating and reusing, it reduces the time of modeling. Now, the interactive visualization system has been integrated into MCAM, as one of its functions, being applied to nuclear analysis.
Keywords
Monte Carlo N-Particle CAD model Monte Carlo Automatic Modeling system Interacitve VisualizationPreview
Unable to display preview. Download preview PDF.
References
- 1.Briesmeister, J.F. (ed.): MCNP – A General Monte Carlo N-Particle Transport Code, Version 4C, Los Alamos National Laboratory, Report LA-13709-M (April 2000)Google Scholar
- 2.Li, Y., Lu, L., Ding, A., Hu, H., Zeng, Q., Zheng, S., et al.: Benchmarking of MCAM 4.0 with the ITER 3D model. Fusion Engineering and Design 82, 2861–2866 (2007)CrossRefGoogle Scholar
- 3.Zeng, Q., Lu, L., Ding, A., et al.: Update of ITER 3D basic neutronics model with MCAM. Fusion Engineering and Design 81, 2773–2778 (2006)CrossRefGoogle Scholar
- 4.Schwarz, R.A., Carter, L.L.: Visual Editor to Create and Display MCNP Input Files. Transaction American Nuclear Society 77, 311–312 (1997)Google Scholar
- 5.
- 6.
- 7.Ostrowski, K., Birman, K., Dolevt, et al.: Programming with Live Distributed Objects. In: Proceedings of the 22nd European Conference on Object-Oriented Programming, July 7 (2008)Google Scholar
- 8.Wu, Y., Li, Y., Lu, L., Ding, A., Hu, H., Zeng, Q., et al.: Research and development of the automatic modeling system for Monte Carlo particle transport simulation. Chinese J. Nuclear Science & Engineering 26(1), 20–27 (2006)Google Scholar
- 9.Wu, Y.C., Xu, X.G.: The Need for Further Development of CAD/MCNP Interface Codes. American Nuclear Society Annual Meeting, Boston, US, June 24-28 (2007)Google Scholar
- 10.Wu, Y.C.: FDS team, CAD-based interface programs for fusion neutron transport simulation. Fusion Engineering and Design 84, 1987–1992 (2009)CrossRefGoogle Scholar
- 11.Arvo, J.: Backward Ray Tracing. Developments in Ray Tracing. ACM Siggraph Course Notes 12, pp. 259-263 (1986)Google Scholar
- 12.Arvo, J., Kirk, D.: Particle Transport and Image Synthesis. Computer Graphics 24(4), 53–66 (1990)CrossRefGoogle Scholar
- 13.Aupperle, L., Harahan, P.: A Hierarchical Illumination Algorithm for Surfaces with Glossy Reflection. Computer Graphics 27(4), 53–66 (1993)Google Scholar
- 14.Cook, R.L.: Distributed Ray Tracing. Computer Graphics 18(3), 137–145 (1984)CrossRefGoogle Scholar
- 15.Lu, L., Lee, Y.K., Zhang, J.J., et al.: Development of Monte Carlo automatic modeling functions of MCAM for TRIPOLI-ITER application. Nuclear Instruments and Methods in Physics Research A 605, 384-387 (2009)Google Scholar
- 16.Wei, G., Zhao, W., Li, Q.: Command Design in the CAD Software. In: Computer Supported Cooperative Work in Design (CSCWD 2007), pp. 768–771 (2007), doi:10.1109/CSCWD.2007.4281533Google Scholar
- 17.Fischer, U., Chen, Y., Simakov, S.P., et al.: Overview of recent progress in IFMIF neutronics. Fusion Engineering and Design 81, 1195–2002 (2006)CrossRefGoogle Scholar