Published October 2011 | Version v1
Journal article

Development of a geometry-coupled visual analysis system for MCNP

  • 1. Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), Hefei, Anhui (China)
  • 2. School of Nuclear Science and Technology, University of Science and Technology of China (USTC), Hefei, Anhui (China)
  • 3. School of Mathematics, Hefei University of Technology (HFUT), Hefei, Anhui (China)

Description

MCNP is a general and powerful Monte Carlo code for photons, neutrons, and electrons transport simulation and is widely used in nuclear analysis. However, external specialized data analysis codes may be needed to analyze complex MCNP calculation results. Especially, there is a lack of efficient data analysis codes which supports geometry-coupled visual analysis. To address the post-processing concerns, a geometry-coupled visual analysis system for MCNP, was developed with 3D scientific visualization and graphics processing unit programming technologies by FDS Team. It was designed and implemented to provide friendly graphical user interface based data manipulation, 3D plotting of tally results, and visual data analysis coupled with geometries. Testing and preliminary application results showed that the system provided a satisfied visual analysis approach for the post-processing of MCNP and obviously enhanced the analysis efficiency. (author)

Availability note (English)

Available from http://dx.doi.org/10.15669/pnst.2.280

Additional details

Identifiers

Publishing Information

Journal Title
Progress in Nuclear Science and Technology
Journal Volume
2
Journal Page Range
p. 280-283
ISSN
2185-4823

Conference

Title
Joint international conference of the 7th supercomputing in nuclear application and the 3rd Monte Carlo
Acronym
SNA+MC 2010
Dates
17-21 Oct 2010
Place
Tokyo (Japan)

Optional Information

Notes
16 refs., 5 figs.