BWR refill-reflood program Task 4. 7: constitutive correlations for shear and heat transfer for the BWR version of TRAC
TRAC (Transient Reactor Analysis Code) is a computer code for best estimate analysis of the thermal hydraulic conditions in a reactor system. The constitutive correlations for shear and heat transfer in the boiling water reactor (BWR) version of TRAC are described. A new model, that accounts for the effect of phase and velocity profiles, has been developed for the interfacial shear and a new set of constitutive correlations are derived. Improvements have been made to the heat transfer in the area of subcooled boiling, boiling transition, and thermal radiation.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Nuclear Engineering Div.
- OSTI ID:
- 6627073
- Report Number(s):
- NUREG/CR-2134; EPRI-NP-1582; GEAP-24940; ON: DE83900713
- Country of Publication:
- United States
- Language:
- English
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