Hydra-TH Simulation of Single-Phase Flow and Heat Transfer in a Rod Bundle Segment.

摘要

The focus of this report is on the comparison of numerical prediction by Hydra-TH of singlephase flow and heat transfer in a segment of Light Water Reactor (LWR) rod bundle geometries with experimental results of Krauss and Meyer. This effort is to support the development of Hydra-TH code, which is a centerpiece of the CASL advanced CFD capability. Single phase flow of air in 37-rod tube bundle is investigated. The rod bundle is similar to that used in experiments by Krauss and Mayer, which has a cross-section as shown in Figure 1 and a total length of 11.50 m with an unheated entrance length of 4.6 m and a heated length of 6.9. While the rod diameter is constant at 0.14 m, the pitch-to-diameter ratio P/D of the rod can be either 1.12 or 1.06. Measurements of flow temperature, velocity and turbulent characteristics are available for the cross-section located at 0.02 m from the outlet.