基于微机的200Wm核供热堆仿真系统PCNHR1.0的研究

Study on PC-Based Simulator for 200Mw Nuclear Heating Reactor

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 ,清华大学核研院研究开发了基于微机的 2 0 0Mw低温核供热堆仿真系统。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 ,WIN DOWS95 /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 200MW 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 PentiumII or above personal computer, under the Windows95/98/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.