RETRAN analysis of multiple steam generator blow down caused by an auxiliary feedwater steam-line break
Analysis results for multiple steam generator blow down caused by an auxiliary feedwater steam-line break performed with the RETRAN-02 MOD 003 computer code are presented to demonstrate the capabilities of the RETRAN code to predict system transient response for verifying changes in operational procedures and supporting plant equipment modifications. A typical four-loop Westinghouse pressurized water reactor was modeled using best-estimate versus worst case licensing assumptions. This paper presents analyses performed to evaluate the necessity of implementing an auxiliary feedwater steam-line isolation modification. RETRAN transient analysis can be used to determine core cooling capability response, departure from nucleate boiling ratio (DNBR) status, and reactor trip signal actuation times.
- OSTI ID:
- 5432490
- Report Number(s):
- CONF-870837-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 54; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
BLOWDOWN
BOILERS
BOILING
COMPUTER CODES
DEPARTURE NUCLEATE BOILING
ENERGY TRANSFER
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
NUCLEATE BOILING
OPERATION
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
R CODES
REACTOR COMPONENTS
REACTOR CORES
REACTOR OPERATION
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
SPECIFICATIONS
STEAM GENERATORS
STEAM LINES
TRANSIENTS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTINGHOUSE STANDARD REACTOR