COMMIX analysis of AP-600 Passive Containment Cooling System

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:6844827

Chang, J F.C.; Chien, T H; Ding, J; Sun, J G; Sha, W T

COMMIX modeling and basic concepts that relate components, i.e., containment, water film cooling, and natural draft air flow systems. of the AP-600 Passive Containment Cooling System are discussed. The critical safety issues during a postulated accident have been identified as (1) maintaining the liquid film outside the steel containment vessel, (2) ensuring the natural convection in the air annulus. and (3) quantifying both heat and mass transfer accurately for the system. The lack of appropriate heat and mass transfer models in the present analysis is addressed. and additional assessment and validation of the proposed models is proposed.

• Research Organization: Argonne National Lab., IL (United States). Materials and Components Technology Div.
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6844827
• Report Number(s): ANL/MCT/CP-77090; CONF-921007-4; ON: DE93002904
• Resource Relation: Conference: 20. water reactor safety information meeting, Bethesda, MD (United States), 21-23 Oct 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTAINMENT
COOLING
PWR TYPE REACTORS
C CODES
DESIGN BASIS ACCIDENTS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
REACTOR COOLING SYSTEMS
REACTOR SAFETY
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
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