Kristian Angele
Vattenfall
Network
Latest external collaboration on country level. Dive into details by clicking on the dots.
Publication
Featured researches published by Kristian Angele.
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance | 2009
Ylva Odemark; Torbjörn M. Green; Kristian Angele; Johan Westin; Farid Alavyoon; Staffan Lundström
New data was obtained for a previously studied T-junction experimental setup [1] for a range of flow ratios between hot and cold flows in order to validate new Large Eddy Simulations (LES). The instantaneous velocity field downstream of the T-junction was measured with two-component Particle Image Velocimetry (PIV) in several horizontal and vertical planes at the centre line downstream of the T-junction. The generated PIV database enables a thorough validation of CFD turbulence statistics. The turbulence statistics are shown to be well predicted despite the fact that the mesh in the LES is rather coarse. By usage of time resolved PIV the temporal evolution of the predominant low frequent large-scale structures, responsible for much of the mixing and the high amplitude temperature fluctuations on the walls, were captured. Those structures are, however, weaker in LES than in PIV, being in line with the fact that the wake region behind the penetrating vertical hot jet is underpredicted in LES. Tests regarding the influence of the LES-results to the shape of the inlet boundary conditions (developed or flat symmetric mean-velocity profiles) were carried out and the sensitivity in the results was shown to be small. Furthermore, the results show good agreement with the experimental data independent of the flow ratio between the hot and the cold flows.Copyright
Physics of Fluids | 2008
Ola Lögdberg; Kristian Angele; P. Henrik Alfredsson
This study focuses on the mean velocity distribution of turbulent boundary layers near, at, and after separation. The proper mean velocity scaling of the outer region in strong adverse pressure gra ...
The Journal of Computational Multiphase Flows | 2012
Edouard Michta; Kai Fu; Henryk Anglart; Kristian Angele
A new model for simulation of bubbly two-phase flows has been developed and implemented into an open-source Computational Fluid Dynamics (CFD) code OpenFOAM. The model employs the two-fluid framework with closure relationships for the interfacial momentum transfer. The bubble size is calculated based on the solution of the interfacial area concentration equations. The predictions are validated against a wide range of experimental data containing measured void fraction, the phasic velocity and the interfacial area concentration. The new model demonstrates the ability to capture the wall peaking of void fraction for small bubbles. The predicted levels of void fraction and phasic velocities are in good agreement with measured data.
18th International Conference on Nuclear Engineering: Volume 4, Parts A and B | 2010
Hernan Tinoco; Hans Lindqvist; Ylva Odemark; Carl-Maikel Högström; Kristian Angele
Two broken control rods and a large number of rods with cracks were found at the inspection carried out during the refueling outage of the twin reactors Oskarshamn 3 and Forsmark 3 in the fall of 2008. As a part of an extensive damage investigation, time dependent CFD simulations of the flow and the heat transfer in the annular region formed by the guide tube and control rod stem were carried out, [1]. The simulations together with metallurgical and structural analyses indicated that the cracks were initiated by thermal fatigue. The knowledge assembled at this stage was sufficient to permit the restart of both reactors at the end of year 2008 conditioned to that further studies to be carried out for clarifying all remaining matters. Additionally, all control rods were inserted 14% to protect the welding region of the stem. Unfortunately, this measure led to new cracks a few months later. This matter will be explained in the second part of this work, [2]. As a part of the accomplished complementary work, new CFD models were developed in conformity with the guidelines of references [3] and [4]. The new results establish the simulation requirements needed to accomplish accurate conjugate heat transfer predictions. Those requirements are much more rigorous than the ones needed for flow simulations without heat transfer. In the present case, URANS simulations, which are less resource consuming than LES simulations, seem to rather accurately describe the mixing process occurring inside the control rod guide tube. Structure mechanics analyses based on the CFD simulations show that the cracks are initiated by thermal fatigue and that their propagation and growth are probably enhanced by mechanical vibrations.Copyright
18th International Conference on Nuclear Engineering: Volume 4, Parts A and B | 2010
Kristian Angele; Mathias Cehlin; Carl-Maikel Högström; Ylva Odemark; Mats Henriksson; Hernan Tinoco; Hans Lindqvist; Bengt Hemström
Alarge number of control rod cracks were detected during therefuelling outage of the twin reactors Oskarshamn 3 and Forsmark3 in the fall of 2008. The extensive damage investigationfinally lead to ...
European Journal of Mechanics B-fluids | 2005
Kristian Angele; Barbro Muhammad-Klingmann
European Journal of Mechanics B-fluids | 2006
Kristian Angele; Barbro Muhammad-Klingmann
Nuclear Engineering and Design | 2013
B.L. Smith; J.H. Mahaffy; Kristian Angele
European Journal of Mechanics B-fluids | 2010
Ola Lögdberg; Kristian Angele; P. Henrik Alfredsson
Nuclear Engineering and Design | 2011
Kristian Angele; Ylva Odemark; Mathias Cehlin; B. Hemström; Carl-Maikel Högström; Mats Henriksson; Hernan Tinoco; Hans Lindqvist