CORMLT code for the analysis of degraded core accidents. Computer code manual. [PWR]
Abstract
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.
- Authors:
- Publication Date:
- Research Org.:
- Science Applications International Corp., Los Altos, CA (USA)
- OSTI Identifier:
- 6120160
- Report Number(s):
- EPRI-NP-3767-CCM
ON: TI85920186
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 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
Citation Formats
Denny, V E. CORMLT code for the analysis of degraded core accidents. Computer code manual. [PWR]. United States: N. p., 1984.
Web.
Denny, V E. CORMLT code for the analysis of degraded core accidents. Computer code manual. [PWR]. United States.
Denny, V E. 1984.
"CORMLT code for the analysis of degraded core accidents. Computer code manual. [PWR]". United States.
@article{osti_6120160,
title = {CORMLT code for the analysis of degraded core accidents. Computer code manual. [PWR]},
author = {Denny, V E},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/6120160},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Dec 01 00:00:00 EST 1984},
month = {Sat Dec 01 00:00:00 EST 1984}
}