Analyses of subcooled CCFL tests for evaluation of W(combining low line)COBRA/TRAC applicability

Nuclear Engineering and Design

Volumn 185, Issue 2-3, 1998, Pages 127-140

  Takeuchi, K ^a   Nissley, M E ^a   Young, M Y ^a  

^a WESTINGHOUSE ELECTRIC COMPANY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

AIR; CODES (SYMBOLS); CORRELATION METHODS; FLOW OF FLUIDS; MATHEMATICAL MODELS; STEAM;

BANKOFF FLOODING CORRELATION; SUBCOOLED COUNTER CURRENT FLOW LIMIT (CCFL) TESTS;

COOLING SYSTEMS;

EID: 0032178688     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0029-5493(98)00246-5     Document Type: Article

References (9)

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3. Boyack, B., et al., 1989. Quantifying reactor safety margins-application of code scaling, applicability, and uncertainty evaluation methodology to a large-break loss-of-coolant accident. NIREG/CR-5249.
4. Colburn, A.P., 1933. A method of correlating forced convection heat transfer data and a comparison with fluid friction. Trans. Am. Inst. Chem. Eng. 29, 174-210.
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8. Takeuchi, K., Young, M.Y., Assessment of flooding in a best estimate thermal hydraulic code (WCOBRA/TRAC), Nucl. Eng. Design (to be published).
9. Thurgood, M.J., Kelly, J.M., Guidotti, T.E., Kobt, R.J., Crowell, K.R., 1982. COBRA/ TRAC - a thermal-hydraulics code for transient analysis of nuclear reactor vessels and primary coolant systems, NUREG/CR-3046, 1982.