학술논문

Effect of dc-power-system reliability on reactor-shutdown cooling. [PWR; BWR]
Document Type
Conference
Author
Source
Conference: American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981
Subject
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS BWR TYPE REACTORS
RHR SYSTEMS
POWER SUPPLIES
RELIABILITY
PWR TYPE REACTORS
AFTER-HEAT REMOVAL
DC SYSTEMS
FAILURES
FAULT TREE ANALYSIS
COOLING SYSTEMS
ELECTRONIC EQUIPMENT
ENERGY SYSTEMS
EQUIPMENT
POWER SYSTEMS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS 210100* -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled
210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
Language
English
Abstract
The DC power systems in a nuclear power plant provide control and motive power to valves, instrumentation, emergency diesel generators, and many other components and systems during all phases of plant operation including abnormal shutdowns and accident situations. A specific area of concern is the adequacy of the minimum design requirements for DC power systems, particularly with regard to multiple and common cause failures. This concern relates to the application of the single failure criterion for assuring a reliable DC power supply which may be required for the functionability of shutdown cooling systems. The results are presented of a reliability based study performed to assess the adequacy of DC power supply design requirements for currently operating light water reactors with particular attention to shutdown cooling requirements.