Coordinated control system design and verification of HTR-PM plant

被引:4
|
作者
Dong, Zhe [1 ]
Pan, Yifei [1 ]
Huang, Xiaojin [1 ]
Dong, Yujie [1 ]
Zhang, Zuoyi [1 ]
机构
[1] Tsinghua Univ, Inst Nucl & New Energy Technol, Collaborat Innovat Ctr Adv Nucl Energy Technol, Key Lab Adv Reactor Engn & Safety,Minist Educ, Beijing 100084, Peoples R China
关键词
HTR-PM; Coordinated control system; Full-scale simulator; SLIDING MODE CONTROL; POWER-PLANTS; REACTORS; FEATURES;
D O I
10.1016/j.nucengdes.2017.11.007
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The modular high temperature reactor (MHTGR), which uses helium as coolant and graphite as both moderator and structural material, has inherent safety features. It is multi-modular, i.e. the superheated steam produced by multiple MHTGR-based nuclear supplying system (NSSS) modules are combined to drive a common thermal load. The inherent safety feature of MHTGR can applied to a large-scale nuclear plant of any desired power ratings by adding modules. Since the plant power control technique of classical single-modular plants cannot be directly applied to multi-modular plants, it is necessary to design a new power control system for multi-modular plants. In this paper, the coordinated control system is presented for the two-module HTR-PM plant, the first multi-modular high temperature gas-cooled nuclear plant to be constructed in the world. The control system design is tested on the full-scale simulator of HTR-PM plant for the cases of power and high ramp down pressure heater bypass. The results demonstrate the feasibility of control system design and the acceptable transient performance of the multi-module plant.
引用
收藏
页码:25 / 33
页数:9
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