Research And Implementation Of A Visual Analysis System For MCNP

MCNP is a general and powerful Monte Carlo N-Particle transport code, which is widely used in the field of reactor physics radiation protection, nuclear detection , aerospace etc. It has geometrical adaptability, high accuracy on calculation and analysis of nuclear physics. As traditional data analysis methods are time-consuming, and poor spatial in analyzing massive data in neutronics transport simulation, they are becoming the bottleneck of neutronics analyses. The need for visualizing the result of neutronics simulation is high demanded.A visual analysis system for MCNP was self-developed at FDS Team by using scientific visualization technology, GPU (graphics processing unit) visual programming technology, and the reversion engine of MCAM (Monte Carlo Automatic Modeling System). The visual analysis system was implemented to support data extraction and manipulation based on graphics user interface, three-dimensional plotting of tally results, and visual analysis of the results with geometries. MCNP output analysis has been more intuitive and effective.The study reports a comprehensive and detailed introduction to the system, including its framework, main functions, development environment and key technologies. And the system has been tested by many de facto cases, such as ITER. Testing results showed that the system provided an intuitively and effectively visual analysis approach for the post-processing of MCNP and obviously enhanced the analysis efficiency.