... reactor core, and can predict the flow characteristics of the coolant in the pressurized water reactor core. This code can provide effective design and research methods for thermal hydraulic analysis of pressurized water reactor fuel assemblies. PWR core subchannel analysis method rod bundle...

... Abstract Past histories of fuel assembly blockage incidents had made investigation of flow channel blockage in rod bundle a compelling field of thermal-hydraulic safety. This study experimentally investigate flow field structural characteristics in a 5 × 5 rod bundle under two sub-channel...

... Abstract Forced convective heat transfer experiment is carried out with a 5 × 5 rod bundle, which consists of square-arranged heating rods and multiple axially spaced grids. Deionized water is used to cool the heating rods, and the experiment is carried out under single-phase conditions...

... Abstract Using deionized water as the working fluid, an experimental study on the resistance characteristics of single-phase and two-phase flow under natural circulation conditions is carried out in a 3 × 3 rod bundle channel. For the single-phase flow, the flow regime transition of rod bundle...

... Abstract In order to clearly understand the phase distributions, the gas-liquid two-phase flow in a 5 × 5 bare rod bundle channel was numerically studied based on the Euler-Euler two fluid model with the CFX commercial software. In the two-phase bubbly flow simulation, the interfacial forces...

... Abstract This paper presents the assessment of the computational fluid dynamics (CFD) methodology for simulating the boiling flow in the Pressurized Water Reactor (PWR) rod bundle. The method includes the Eulerian-Eulerian two-fluid model coupled with the improved wall heat partitioning model...

...-physics phenomena. This study uses Computational Fluid Dynamics (CFD) Lagrangian Particle Tracking (LPT) techniques in analysis of particle transfer behavior in fuel rod bundles focusing on flow swirl and turbulence impacts. It is hoped that high fidelity CFD results can provide insights into particle...

... Abstract The floating reactor system will be rolling, heaving and other movements affected by waves, wind, etc. These motions will introduce additional inertial force field into the rod bundle, thus affecting the flow characteristics in the rod bundle channel. In order to study the influence...

... Abstract In relation to the modeling of the one-dimensional interfacial area transport equation for an adiabatic bubbly flow in a vertical rod bundle, some existing models of sink and source terms were reviewed and evaluated. Based on the reviewed interaction mechanisms of bubbles and turbulent...

... 08 04 2011 Rod bundles are widely used in industry today with applications ranging from nuclear reactors, heat exchangers, and steam generators. Accurately modeling the inherently unsteady and turbulent flow within these rods is essential in order to design for optimal efficiency while...

... by using state-of-the-art measurement techniques that may elucidate the fundamental physics of fluid flow in rod bundles with spacer grids. In particular, this work aims to develop an experimental data base with high spatial and temporal resolution of flow measurements inside a 5×5 rod bundles with spacer...

... 17 09 2008 The direct numerical simulation, extended to boundary-fitted coordinate, has been carried out for a fully-developed turbulent flow thermal hydraulics in a triangular rod bundle. The rod bundle is premised to be an infinite array. The spacer grid effects are ignored...