FLOW COASTDOWN IN CENTRIFUGAL PUMP SYSTEMS

被引：16

作者：

YOKOMURA, T

机构：

[1] Ship Research Institute, Ministry of Transportation, Mitaka, Tokyo

来源：

NUCLEAR ENGINEERING AND DESIGN | 1969年 / 10卷 / 02期

关键词：

D O I：

10.1016/0029-5493(69)90044-2

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：

This report describes an analytical method to estimate coastdown behaviour in indirect cycle water-cooled reactor systems. This method is applicable to a system with one reactor and any number of centrifugal pumps. The detailed information of the pump characteristics is not required. Numerical results of the analysis are presented and compared with experiments performed on a reactor model system. Agreement between the analysis and experiment is satisfactory in a case, where all pumps lose the power simultaneously. In another case of one pump power failure, observed flow rate is found to be in a range predicted by analysis. © 1969.

引用

页码：250 / &