Hassan, Yassin A.. Design of new facility for bypass flow experiment. (). King Mongkut's University of Technology North Bangkok. Central Library. : , 2011.
Abstract:
Bypass flow in prismatic core of very high temperature gas-cooled reactor (VHTR) is an important feature in the reactor core design of Generation IV reactor. Although many researchers have investigated about flows in VHTR for a long time, details of thermal/hydraulic characteristics of flows in this reactor core type still are not fully understood. As starting of bypass flow project, old facility was designed to assess the methods of flow measurement including PIV technique to enhance the understanding about bypass flow.
In preliminary study, basic characteristics of air flow in the model of prismatic core of VHTR were studied experimentally and numerically based on old facility. All results were matched successfully but flow similarities between experiment and actual operation of reactor core could not be attained. In the first step of new facility design, the concept of multiple-path flow is employed by matching pressure drop of each flow passage. Because the results of this design show some unfavorable features, another concept starting from specifying mass flow rate based on flow area ratio is applied and examined by numerical simulations. The compromised design of new facility is met after performing few simulations.
King Mongkut's University of Technology North Bangkok. Central Library