PWR LOSS-OF-COOLANT ACCIDENT CORE MELTDOWN CALCULATIONS

Technical Report · Wed May 01 04:00:00 EDT 1957

DOI:https://doi.org/10.2172/4318539· OSTI ID:4318539

Swartz, L M; Lemmon, Jr, A W; Hulbert, L E

Results are presented of a study made of the possible extent of zirconium-water reaction and core meltdown following a postulated loss-of-coolant accident in the PWR plant. Zirconium-water chemical reaction and core meltdown occur in the course of the core temperature excursion which could follow a loss- of-coolant if no cooling were provided after an uncovering of the core. An analysis of the temperature excursion involves consideration or the complex relationships between core geometry, decay heating rates, water (or steam) flow through the core, and the thermodynamic and chemical properties of water, steam, and the core materials. Parametric studies of the temperature excursion are used in evaluating the effectiveness of the PWR Safety Injection System in prevention of core chemical reaction and meltdown. Combinations of delay time in operation and rate of injection are considered. (auth)

• Research Organization: Westinghouse Electric Corp. Bettis Plant, Pittsburgh; Battelle Memorial Inst., Columbus, Ohio (US)
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-12-002531
• OSTI ID: 4318539
• Report Number(s): WAPD-SC-544
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
CHEMICAL REACTIONS
CONFIGURATION
CONTROL SYSTEMS
COOLANT LOOPS
DECAY
EXCURSIONS
FLUID FLOW
HEAT TRANSFER
HIGH TEMPERATURE
LEAKS
MECHANICAL STRUCTURES
MELTING
NUMERICALS
PHYSICS
PRESSURE
REACTOR CORE
REACTOR SAFETY
REACTORS
STEAM
THERMODYNAMICS
WATER
WATER COOLANT
ZIRCONIUM