Development and verification of Design and Simulation System for Digital Reactor Fluid Instruction Control System

被引:0
作者
Wang Ya-feng [1 ]
Liu Dong [1 ]
Liu Ying [1 ]
Yu Yang [1 ]
Li Song-wei [1 ]
Cao Guo-hai [1 ]
Pang Bo [1 ]
Lu Tian-yu [1 ]
机构
[1] Nucl Power Inst China, Sci & Technol Reactor Syst Design Technol Lab, Chengdu 610041, Sichuan, Peoples R China
来源
2018 INTERNATIONAL CONFERENCE ON POWER SYSTEM TECHNOLOGY (POWERCON) | 2018年
关键词
Fluid Instrument Control System; Visualization design; HMI; ACP1000;
D O I
暂无
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
In order to realize the transient and accident analysis of reactor system and verification of system control scheme, the latest computer technology is used to develop advanced graphical modeling tool for TRANTH code, the human-machine interaction interface, and integration research between software and digital reactor design and verification platform, so as to the design and simulation system of digital reactor fluid instruction control system is built up. The nuclear power plant (ACP1000) is chosen as a research object some typical operating conditions are selected and executed. Results show that the design and simulation system can implement the modeling, calculation, interactive manipulation and display of reactor fluid instruction control system, which brings a multi-professional joint simulation of reactor fluid instruction control system to fruition, and provides technology support for rapid generation, evaluation, verification and optimization of design scheme about reactor fluid instruction control system.
引用
收藏
页码:4751 / 4755
页数:5
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