Reliability of the Coolant Flow Rate Measuring System at the Ignalina Nuclear Power Plant

被引：0

作者：

Yu. Augutis

E. Uspuras

R. Alzbutas

V. Matuzas

机构：

[1] Vitautas Velikii University,

[2] Lithuanian Power-Engineering Institute,undefined

[3] Lithuanian Power-Engineering Institute,undefined

来源：

Atomic Energy | 2004年 / 96卷

关键词：

Mathematical Model; Power Plant; Measurement System; Nuclear Power Plant; Reliability Estimate;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

Age assessment and control of the reliability of the coolant flow-rate measurement system of the RBMK-1500 reactor at the Ignalina nuclear power plant are examined. A statistical analysis is made of the data obtained from measurements of the techanical characteristics of SHADR-32M flow meters. A mathematical model of the aging of flow meters and reliability estimates is constructed. A strategy is developed for replacing SHADR; this strategy makes it possible to support the required relaibility of the entire coolant flow-rate measurement system.

引用

页码：403 / 406

页数：3