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Interactive visualization of MCNP-based neutronics models

  • Junjun Zhang
  • , Pengcheng Long
  • , Guozhong Wang
  • , Jian Xiong
  • , Dianxi Wang
  • , Qin Zeng
  • , Yican Wu
  • CAS - Institute of Plasma Physics
  • University of Science and Technology of China

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

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.

Original languageEnglish
Title of host publicationProceedings of the 2011 International Conference on Informatics, Cybernetics, and Computer Engineering (ICCE2011) November 19-20, 2011, Melbourne, Australia
Subtitle of host publicationVolume 3: Computer Networks and Electronic
EditorsLiangzhong Jiang
Pages125-131
Number of pages7
DOIs
StatePublished - 2011

Publication series

NameAdvances in Intelligent and Soft Computing
Volume112
ISSN (Print)1867-5662

Keywords

  • CAD model
  • Interacitve Visualization
  • Monte Carlo Automatic Modeling system
  • Monte Carlo N-Particle

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