Analysis of Load-following Operation Capability of Large Sodium-cooled Fast Reactor

被引：0

作者：

Dai R. ^{[1
]}

Duan T. ^{[1
]}

Liu Y. ^{[1
]}

Zhang H. ^{[2
]}

Zhang W. ^{[1
]}

Xu W. ^{[1
]}

机构：

[1] China Institute of Atomic Energy, Beijing

[2] North Regional Office of Nuclear and Radiation Safety Inspection, National Nuclear Safety Administration, Beijing

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2023年 / 44卷 / 06期

关键词：

Load-following; Once-through steam generator(OTSG); Simulation; Simulink; Sodium-cooled fast reactor;

D O I：

10.13832/j.jnpe.2023.06.0199

中图分类号：

学科分类号：

摘要：

In order to study the load-following capability of a large sodium-cooled fast reactor in China, a simulation model of the whole system of this sodium-cooled fast reactor is established based on MATLAB/Simulink platform, and the load-following capability of the primary, second and third loops of the fast reactor system is tested in different levels under the extreme condition of load step and no control system intervention. The simulation results show that the primary and second loops of the fast reactor system can withstand ±10% of the load step, while the load-following capability of the third loop cannot meet this requirement. Under the current process design and key parameter limit conditions, this large sodium-cooled fast reactor has a poor load-following operation capability, and it cannot withstand a 10% load step. When operating at 90%Pn power level, it can withstand a 2.9% load step increase at most, and its once-through steam generator(OTSG) is the main limiting factor. © 2023 Atomic Energy Press. All rights reserved.

引用

页码：199 / 205

页数：6

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