PWR systems transient analysis

Conference · Thu Jan 01 00:00:00 EST 1981

OSTI ID:6210743

Kennedy, M F

The transient analysis of pressurized-water-reactor (PWR) systems involves the assessment of the response of the total plant including primary and secondary coolant systems, steam piping and turbine (possibly including the complete feedwater train), and various control and safety systems to a number of event sequences which are developed by considering possible failures or maloperations of plant components. This analysis is performed as part of the plant safety analysis to insure the adequacy of the reactor design and operating procedures and to verify the applicable plant emergency guidelines. The event sequences which are considered vary in severity (and calculational difficulty) from a series of normal operational transients including minor load changes, reactor trips, valve and pump malfunctions up to the double-ended guillotine rupture of a primary reactor coolant system pipe. The focus of this discussion is on the analysis of all transients and accidents excluding the loss of coolant accident.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6210743
• Report Number(s): CONF-8110264-2; ON: DE83009576
• Resource Relation: Conference: ANL/International Centre for Heat and Mass Transfer course on LWRs, Belgrad, Yugoslavia, 11 Oct 1981; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
TRANSIENTS
HEAT TRANSFER
HYDRAULICS
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled