Evaluation of intersubchannel mixing in a simulated nuclear fuel rod bundle using a gamma camera

Single-phase, isothermal turbulent and forced mixing data were obtained from two and three-subchannel simulations of a nuclear fuel assembly using a gamma-camera imaging system. One of the two or three inlet streams was traced with the gamma emitting radionuclide 99m-Tc pertechnetate, and axial subchannel concentration gradients were measured as a function of gap spacing and Reynolds number over the respective ranges 0.050 to 0.197 inch, and 3000 to 20,000. The gamma camera allowed external monitoring over the axial length of the test assembly thereby eliminating experimental problems associated with flow partitioning and withdrawal systems. In addition, it provided a methodology for making noninvasive measurements under operating conditions downstream of a mixing vane and over the active region of diversion crossflow. The missing parameter β, defined as the ratio of the transverse to axial mass velocities, was found to be relatively independent of the pitch to rod diameter ratio for gap spaces of 0.100, 0.157, and 0.197 inches, but was observed to increase sharply for the smallest gap spacing (0.050 inch) at a constant Reynolds number. Diversion crossflow was characterized by providing fixed but different flow rate to each subchannel