基于微机的核供热堆模拟器PCNHR1.0的软件系统研究  

Study on Software System of PC-Based Simulator(PCNHR)for 200MW Nuclear Heating Reactor

作　　者：陆冬森[1] 张作义[1] 时振刚[1] 刘杰[1] 陈晓明[1] 

机构地区：[1]清华大学核能技术设计研究院,北京102201

出　　处：《核动力工程》2000年第4期372-377,共6页Nuclear Power Engineering

基　　金：国际原子能机构(IAEA)支持项目

摘　　要：为了使更多的技术人员形象地了解低温堆供热站的原理，在国际原子能机构的支持下，清华大学核能技术设计研究院研究开发了基于微机的200MW低温核供热堆模拟器。它采用两回路、一维漂移流热工水力学模型，点中子堆物理以及控制系统模型，能对核供热堆的稳态运行、瞬态过程和事故进行仿真，仿真精度接近系统分析结果。在奔腾或以上的微机上，WINDOWS95／98／NT操作系统下，能对过程进行实时仿真，而且大多数过程能达到10倍以上超实时。软件采用VisualC＋＋和FORTRAN混合语言编程，运用先进的多线程编程模型、进程通讯和进程控制技术，实现了耦合计算和同步控制。In order to introduce visually the principle of Low-Temperature Nuclear Heating Reactor (NHR) to engineers and scientists, the Institute of Nuclear Energy Technology (INET) in Tsinghua Univ. develops the PC-based Simulator (PCNHR) for 200 MW Nuclear Heating Reactor with the support of IAEA. PCNHR includes a homogeneous mixture model and a dynamic slip model as the thermal-hydraulic model for the reactor cooling system, a point neutron kinetics model for reactor core, protect system and control system models. The steady operation, dynamic state and accident & incident process of NHR are successfully simulated, with a result in close proximity to those from Safety analysis report. All the processes are simulated in real time, also the ability to accelerate the simulation is included. The simulator is run in P Ⅱ or ahave personal computer, under the windos95/98/NT operation system, and developed by mixed-language programming of Visual C++ and Fortran, with multi-thread program model and multi-process communication & process control technology.

关 键 词：核供热堆 混合语言编程 模拟器 软件系统 

分 类 号：TL413.2[核科学技术—核技术及应用] TP319[自动化与计算机技术—计算机软件与理论]