Flow area blokage effect on the coolant rate distribution fast reactor fuel element bundle model

The results of studies of the coolant rate distribution in a blocked rod bundle are given. The experiments were carried out on a simplified fast reactor fuel bundle model. The model consists of 19 tubes (elements) located in a triangular lattice and encased in a hexahedral shell. The ratio of the lattice pitch and element diameter is 1.17, element diameter is 19 mm, average in model cross section coolant rate is 0.5-2.5 m/s, part of blocked bundle cross section is 0.55, Reynolds number is (6.7-33)x103. The integral and local regularities of coolant flow along the perimeter and length of typical elements (central, intermediate, lateral, angular) are found. The results of studies obtained using an electromagnetic transducer of local action are compared with the data of other authors