The addition and assessment of condensation heat transfer models to COBRA-NC for improved analyses of current and advanced reactor containments
Although several computer codes exist which offer the ability to simulate the response of containments to hypothesized events, one appears to offer more in the area of best estimate performance during normal operations and following an accident prior to the release of fission products. This computer code is COBRA-NC due to its ability to analyze the containment multi-dimensionally, to track several species of noncondensible gases, entrained liquid and liquid films throughout the containment, and have the ability to analyze the containment in a passive mode of operation when the only driving forces present are due to natural circulation. Objectives specific to this task were to: enhance the ability of COBRA-NC to analyze both current and advanced reactor containments; and assess the ability, stability and biases of the condensation heat transfer correlations which may be used in containment analyses performed by the utilities and their regulators. 23 refs., 21 figs., 2 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6534576
- Report Number(s):
- EGG-EAST-8270; ON: DE89004949
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
CONTAINMENT SYSTEMS
RESEARCH AND TEST REACTORS
REACTOR SAFETY
C CODES
ENGINEERING DRAWINGS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
NUMERICAL DATA
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