Dynamic analysis of the condensate feedwater system in boiling water reactor plants

Journal Article · Sat May 01 00:00:00 EDT 1982 · Nucl. Technol.; (United States)

OSTI ID:6816811

Tanji, J; Omori, T

The computer code, CONFAC, has been developed for dynamic analysis of the condensate feedwater system in boiling water reactor plants. This code simulates the hydrodynamics in the piping system, the pump dynamics, and the feedwater controller in order to clarify the system transient characteristics in such cases as pump trip incidents. Code verification was performed by comparison between analytical results and actual plant operational data. Satisfactory agreement was obtained. With the code, appropriate pump start/stop interlocks were estimated for preventing pump cavitation in pump trip incidents.

• Research Organization: Hitachi Energy Research Laboratory, Hitachi, Ltd. 1168 Moriyama-cho, Hitachi-shi, Ibaraki-ken 316
• OSTI ID: 6816811
• Journal Information: Nucl. Technol.; (United States), Vol. 57:2
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR COOLING SYSTEMS
COMPUTER CODES
C CODES
FEEDWATER
FLUID-STRUCTURE INTERACTIONS
HYDRODYNAMICS
COMPUTERIZED SIMULATION
FLOW REGULATORS
ACCURACY
CAVITATION
CONDENSATES
NUCLEAR POWER PLANTS
PIPES
PUMPS
SYSTEMS ANALYSIS
TRANSIENTS
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
EQUIPMENT
FLUID MECHANICS
HYDROGEN COMPOUNDS
MECHANICS
NUCLEAR FACILITIES
OXYGEN COMPOUNDS
POWER PLANTS
REACTOR COMPONENTS
REACTORS
SIMULATION
THERMAL POWER PLANTS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled