跳到主要导航 跳到搜索 跳到主要内容

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

科研成果: 书/报告/会议事项章节会议稿件同行评审

摘要

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.

源语言英语
主期刊名Proceedings of the 2011 International Conference on Informatics, Cybernetics, and Computer Engineering (ICCE2011) November 19-20, 2011, Melbourne, Australia
主期刊副标题Volume 3: Computer Networks and Electronic
编辑Liangzhong Jiang
125-131
页数7
DOI
出版状态已出版 - 2011

出版系列

姓名Advances in Intelligent and Soft Computing
112
ISSN(印刷版)1867-5662

学术指纹

探究 'Interactive visualization of MCNP-based neutronics models' 的科研主题。它们共同构成独一无二的学术指纹。

引用此