###

计算机系统应用英文版:2019,28(9):118-124

View/Add Comment 过刊浏览高级检索 HTML

←前一篇 | 后一篇→

码上扫一扫！

下载全文

氚扩散虚拟仿真系统原型研发及其应用

曹欢^1,2, 杨子辉², 俞盛朋², 霍前超², 王海霞², 王芳²

(1.安徽大学物质科学与信息技术研究院, 合肥 230601;2.中国科学院核能安全技术研究所中子输运理论与辐射安全重点实验室, 合肥 230031)

Development and Application of Tritium Diffusion Simulation Prototype System

CAO Huan^1,2, YANG Zi-Hui², YU Sheng-Peng², HUO Qian-Chao², WANG Hai-Xia², WANG Fang²

(1.Institute of Physical Science and Information Technology, Anhui University, Hefei 230601, China;2.Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China)

摘要

图/表

参考文献

相似文献

本文已被：浏览 1347次下载 1680次
Received:February 22, 2019 Revised:March 08, 2019

中文摘要: 为了研究氚泄漏时的动态扩散机制与事故风险，本文基于三维图形引擎研发了氚扩散虚拟仿真系统.采用预先危险性分析方法进行了氚系统安全分析，通过粒子系统方法模拟了事故中氚扩散的动态过程，基于虚拟漫游与仿真技术实现了人机交互仿真功能.以国际热核聚变实验堆（ITER）的氚提取系统仿真为案例，模拟了氢同位素分离柱与管道发生泄漏时氚的动态扩散过程和浓度变化情况，仿真结果为氚泄漏的安全防护提供了依据.

中文关键词: 氚泄漏动态扩散虚拟仿真粒子系统

Abstract:In order to study the dynamic diffusion mechanism and accident risk of tritium, a virtual simulation system for tritium diffusion based on the 3D graphics engine is developed. The accident simulation object is determined by the preliminary hazard analysis method for tritium system. The particle system is applied to simulate the dynamic process of the tritium diffusion, and the human-computer interaction function is realized based on virtual roaming and simulation technology. Finally, take the Tritium extraction system in the International Thermal nuclear Experimental Reactor (ITER) as an example, the dynamic diffusion process and concentration change of tritium is simulated when the hydrogen isotope separation column and pipeline leak. The simulation results provide a basis for the development of safety protection measures when tritium leaks.

keywords: tritium leakage dynamic diffusion virtual simulation particle system

文章编号： 中图分类号： 文献标志码：

基金项目:国家重点研发计划政府间国际科技创新合作专项（2017YFE0300305）；中国科学院信息化项目（XXH13506-104）；安徽省重大科技专项（18030801135）

Author Name	Affiliation	E-mail
CAO Huan	Institute of Physical Science and Information Technology, Anhui University, Hefei 230601, China Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
YANG Zi-Hui	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
YU Sheng-Peng	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
HUO Qian-Chao	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
WANG Hai-Xia	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
WANG Fang	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China	fang.wang@fds.org.cn

Author Name	Affiliation	E-mail
CAO Huan	Institute of Physical Science and Information Technology, Anhui University, Hefei 230601, China Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
YANG Zi-Hui	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
YU Sheng-Peng	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
HUO Qian-Chao	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
WANG Hai-Xia	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
WANG Fang	Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China	fang.wang@fds.org.cn

引用文本：
曹欢,杨子辉,俞盛朋,霍前超,王海霞,王芳.氚扩散虚拟仿真系统原型研发及其应用.计算机系统应用,2019,28(9):118-124
CAO Huan,YANG Zi-Hui,YU Sheng-Peng,HUO Qian-Chao,WANG Hai-Xia,WANG Fang.Development and Application of Tritium Diffusion Simulation Prototype System.COMPUTER SYSTEMS APPLICATIONS,2019,28(9):118-124