CORMLT code for the analysis of degraded core accidents. Computer code manual. [PWR]

Technical Report · Sat Dec 01 00:00:00 EST 1984

OSTI ID:6120160

Denny, V E

A computer code (CORMLT) has been developed to predict the effects of bouyancy-driven convection on the progression of core-degrading accidents in PWR vessels. Thermal/hydraulics modeling includes the downcomer/bottom-head regions, as well as the upper vessel and adjacent hot-leg portions of the primary coolant system for which gas communication is limited to the intervening discharge nozzles (so-called dead-end volumes). CORMLT requires flow rates and temperatures of any water feed (to the downcomer) versus time. CORMLT provides composition, enthalpy, temperature, and flow rate of steam/hydrogen mixtures within the vessel above the (receding) water surface, as well as estimates of these quantities for interaction between the plenum and the rest of the PCS. CORMLT also provides graphical representations for the morphological behavior of the progression of core meltdown accidents.

• Research Organization: Science Applications International Corp., Los Altos, CA (USA)
• OSTI ID: 6120160
• Report Number(s): EPRI-NP-3767-CCM; ON: TI85920186
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MELTDOWN
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
COMPUTER CALCULATIONS
CORIUM
LIQUID FLOW
PRESSURE VESSELS
REACTOR SAFETY
TEMPERATURE GRADIENTS
THEORETICAL DATA
ACCIDENTS
CONTAINERS
DATA
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
INFORMATION
MECHANICS
NUMERICAL DATA
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled