PWR loss of feedwater ATWS: analysis and sensitivity study
Conference
·
OSTI ID:5912473
The incident at the Salem Nuclear plant has presented a renewed interest in the analysis of the consequences of anticipated transients without scram (ATWS). This paper presents the results of an analysis of a complete loss of feedwater ATWS for a typical 4-loop PWR. The loss of feedwater transient was selected since previous analyses have shown that this transient produces one of the more limiting overpressure conditions in the primary system. These results provide a detailed analysis of this transient using current analytical techniques and show the sensitivity to several important parameters and plant modeling techniques. The RELAP5/MOD1 computer code has been used for this analysis. The code version is designated as Cycle 13 with additional modifications provided by both INEL and BNL.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5912473
- Report Number(s):
- BNL-NUREG-33529; CONF-831047-82; ON: DE83017344
- Country of Publication:
- United States
- Language:
- English
Similar Records
Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT facility. [PWR]
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Technical Report
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5492521
Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT Facility
Journal Article
·
Fri Jul 01 00:00:00 EDT 1983
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:6693595
Steam generator behavior during loss-of-feedwater and loss-of-offsite-power ATWS experiments in LOFT
Conference
·
Mon Oct 31 23:00:00 EST 1983
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:6930555
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
COMPUTER CALCULATIONS
ENERGY TRANSFER
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MECHANICS
OXYGEN COMPOUNDS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
COMPUTER CALCULATIONS
ENERGY TRANSFER
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MECHANICS
OXYGEN COMPOUNDS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS