Home / Publications / Journals / Nuclear Technology / Volume 105 / Number 2
Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 190-200
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34922
Articles are hosted by Taylor and Francis Online.
In order to study the thermohydraulic behavior of a natural-circulation-cooled boiling water reactor (BWR) fuel assembly, such as void drift, flow pattern distribution, and stability, a scaled loop geometry is designed. For modeling the steam/water flow in a BWR fuel assembly, scaling criteria are derived using the onedimensional drift-flux model. Thermal equilibrium and subcooled boiling conditions are treated separately, resulting in one overall set of criteria. Scaling on all flow regimes that can be present in a normal fuel assembly leads to fixing both the assembly mass flux and the geometric dimensions. When Freon-12 is used as a modeling fluid, model assembly dimensions must be 0.46 of the prototype. Total power consumption must be reduced by a factor 50. To sustain cooling by natural circulation, a modeled chimney and downcomer are included.