小型模块式反应堆（Small Modular Reactor, SMR）普遍具有固有安全性特征，是核能发展的重要方向。为了保证安全性、实现经济性并满足多用途需要，可利用多套基于SMR的核蒸汽供应系统（Nuclear Steam Supply System, NSSS）模块驱动多个负荷模块构建多模块大型核动力机组。相比于单模块核动力机组，多模块机组的多个NSSS模块及负荷模块之间具有较强的耦合特性，需要建立反映此耦合特性的多模块核能机组动态模型，以满足控制系统设计和验证的需求。本文面向我国研制基于模块式高温气冷堆（Modular High Temperature Gas-cooled Reactor, MHTGR）及低温核供热堆 (Nuclear Heating Reactor, NHR)的多模块核能机组控制方法及系统的重大需求，建立了汽轮机组、区域供热站、海水淡化装置等负荷模块以及蒸汽及给水流体网络的动态模型，并利用已有NSSS模块动态模型通过系统集成建立了具有“多堆带一机”结构的6模块高温气冷堆核电站HTR-PM600和具有“一堆带多机”功能的NHR200-II低温堆机组的动态模型。利用MATLAB/SIMULINK开发平台研制了数值仿真软件，开展了开环动态特性仿真验证和闭环动态特性仿真分析，不仅验证了动态模型的适用性而且给出了多模块核能机组HTR-PM600和NHR200-II的协调控制性能。本文给出的负荷模块和流体网络动态模型也可以用于建立基于其它类型SMR的多模块核动力机组，对机组动态特性分析和控制系统设计具有重要价值。进一步的工作是发展“多堆带多机”机组的动态模型，进一步深入开展大型多用途核能机组的控制系统研究。

The small modular reactor (SMR) generally have inherent security features, playing an important role in the development of nuclear energy. It is valuable to combine multiple SMR nuclear steam supply system (NSSS) modules with multiple load modules to construct the multi-module large-scale nuclear power system, ensuring the safety, achieving the economy and meeting multi-purpose needs. However, there are strong coupling characteristics between multiple NSSS modules and load modules compared to one-modular nuclear power system, which make it necessary to establish the dynamic model of the multi-module nuclear power system to design and validate the control system of the plant.In this paper, considering the demand in design of the control strategy and control system for both Modular High Temperature Gas-cooled Reactor (MHTGR) based and Nuclear Heating Reactor (NHR) based multi-module nuclear power systems, the dynamic models of steam turbine unit, regional heat supply station, seawater desalination unit and the fluid flow network of steam and feed water are established. Combining those models with the existing NSSS module models, the dynamic model of the Multi-NSSS with One-Load type HTR-PM600 plant and the One-NSSS with Multi-Load type NHR-200II cogeneration plant are integrated respectively. Finally, numerical simulation software of those two plant models are implemented in the MATLAB/SIMULINK development platform, with which the open-loop simulations and closed-loop simulations are conducted to verified the applicability of those dynamic models and give the coordinated control performance of both HTR-PM600 and NHR200-II multi-module plant. Load models and the dynamic model of fluid flow network in this paper can also be used in establishing other SMR-based multi-module nuclear power plant, valuable in dynamic characteristics analysis and control system design. The further work is to develop the dynamic models of Multi-NSSS & Multi-Load plants and perform further research on the control system of large multi-purpose nuclear power units.