Quasi-static core liquid level depression and long-term core uncovery during a PWR LOCA

Journal Article · · Nuclear Safety

OSTI ID:7108694

Kukita, Y; Nakamura, H ^[1]; Schultz, R R ^[2]; Katayama, J ^[3]

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1. Japan Atomic Energy Research Institute, Tokai-Mura, Ibaraki-Ken (Japan)
2. Idaho National Engineering Lab., Idaho Falls, ID (United States)
3. Muroran Institute of Technology, Muroran-Shi, Hokkaido (Japan)

The possibility exists that the core liquid level can be depressed quasi-statically during long-term plant cooldown following a cold-leg-break loss-of-coolant accident in a pressurized-water reactor. Such a level depression can take place if the core steaming rate is almost balanced with the steam condensation rate in the reactor coolant system (RCS). Integral experiments simulating three steam condensation modes in the RCS have shown that quasi-static level depressions can happen and thus have the potential for causing a prolonged uncovery and heatup of the core upper regions.

• DOE Contract Number: AC07-76ID01570
• OSTI ID: 7108694
• Journal Information: Nuclear Safety, Vol. 34, Issue 1; ISSN 0029-5604
• 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
LOSS OF COOLANT
PRIMARY COOLANT CIRCUITS
COOLANTS
REACTOR CORES
REACTOR SAFETY
STEAM
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled