Existence of early core rewet during large-break LOCA transients in a commercial PWR

Conference · Fri Jan 01 04:00:00 EST 1982

OSTI ID:6733796

Demmie, P N

Large-break experiments in the Loss-of-Fluid Test (LOFT) Facility showed that the nuclear fuel rods were rewet between 5 and 10 s after break initiation. Computer calculations of large-break loss-of-coolant accident (LOCA) transients in a commercial pressurized water reactor (PWR) predict similar early core rewets if the primary coolant pumps remain powered. A question suggested by these experiments and calculations is, Can system conditions exist in a commercial PWR which would prevent an early core rewet during a large-break LOCA transient. A computer study answered this question in the affirmative for 200%, double-ended, cold-leg break LOCA transients in a PWR of the Westinghouse four-loop design. However, the probability of such an accident actually occurring is extremely small. This paper summarizes the results of this study and briefly discusses the implications of these results on nuclear safety issues.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6733796
• Report Number(s): EGG-M-17782; CONF-820802-30; ON: DE83000537
• Country of Publication: United States
• Language: English

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
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS