COBRA/TRAC analysis of the PKL reflood test K9

Conference · Mon Mar 01 00:00:00 EST 1982

OSTI ID:6885309

Wilkins, C A

Experiments simulating the refill and reflood procedure after a loss-of-coolant accident (LOCA) in a 1300 MW PWR primary coolant system were performed at the KWU test facility in Erlangen, Germany. COBRA/TRAC was used to model experiment K9 of the PKL series (completed December 1979). PKL-K9 was characterized by a double-ended guillotine break in the cold leg with emergency core cooling water injected into the cold legs. COBRA/TRAC was able to successfully predict lower core temperature profiles and quench times, upper core temperature profiles until quench, upper plenum and break pressures and correct trends in collapsed water levels.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6885309
• Report Number(s): PNL-SA-10233; CONF-820802-50; ON: DE83002668
• Resource Relation: Conference: International meeting on thermal nuclear reactor safety, Chicago, IL, USA, 29 Aug 1982
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
SIMULATION
PWR TYPE REACTORS
C CODES
COMPUTER CALCULATIONS
COMPUTER CODES
ECCS
ACCIDENTS
ENGINEERED SAFETY SYSTEMS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled