Control of a high temperature Supercritical pressure light water cooled and moderated reactor with water rods

被引:48
作者
Ishiwatari, Y [1 ]
Oka, Y [1 ]
Koshizuka, S [1 ]
机构
[1] Univ Tokyo, Nucl Engn Res Lab, Naka, Ibaraki 3191188, Japan
关键词
supercritical pressure; once-through cycle; descending flow water rod; step response; control system;
D O I
10.3327/jnst.40.298
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 [核科学与技术]; 082701 [核能科学与工程];
摘要
The plant system of a supercritical pressure light water reactor (SCR) is once-through direct cycle. The whole coolant from the feedwater pumps is driven to the turbines. The core flow rate is less than 1/7 of that of a boiling water reactor. In the present design of the high temperature thermal reactor (SCLWR-H), the fuel assemblies contain many water rods in which the coolant flows downward. The stepwise responses of the SCLWR-H are analyzed against perturbations without a control system. Based on these analyses, a control system of the SCLWR-H is designed. The pressure is controlled by the turbine control valves. The main steam temperature is controlled by the feedwater pumps. The reactor power is controlled by the control rods. The control parameters are optimized by the test calculations to satisfy the criteria of both fast convergence and stability. The reactor is controlled stably with the designed control systems against various perturbations, such as setpoint change of the pressure, the main steam temperature and the core power, decrease in the feedwater temperature, and decrease in the feedwater flow rate.
引用
收藏
页码:298 / 306
页数:9
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