MAYU04: a method to evaluate transient thermal hydraulic conditions in rod bundles. [BWR]
Technical Report
·
OSTI ID:7301923
The technical basis and numerical calculations performed by the code MAYU04 are described. The code analyzes one-dimensional single channel hydraulic and heat transfer transients in rod bundles and calculates local hydraulic conditions and skin heater or fuel rod heat transfer information (i.e., temperature and heat transfer coefficients). Numerous simplifications are made in the solution of the two-phase flow equations, notably that of thermodynamic equilibrium. However, the drift flux formulation employed is particularly useful in handling problems typical of the loss-of-coolant accident analysis. The equations are valid for cocurrent and countercurrent flow. The treatment of countercurrent flow limiting (CCFL) at the bundle exit and the propagation of two-phase mixture levels are also included. The model is suited for BWR LOCA analysis where pressure transients are not very severe and subcooled voids are not very important.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Boiling Water Reactor Systems Dept.
- OSTI ID:
- 7301923
- Report Number(s):
- GEAP-23517
- Country of Publication:
- United States
- Language:
- English
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