Onsala Ingenjörsbyrå AB
References
Onsala Ingenjörsbyrå AB
Published
K. Nilsson and F. Tornberg | Computers & Structures Vol. 216, pp 1-14, 2019
“On blowdown analysis with efficient and reliable direct time integration methods for wave propagation and fluid-structure-interaction response”
Jens Conzen, Manager, Structural Services & Vibration, Fauske & Associates, LLC, Pascal Veber, PhD, CEO, Onsala Ingenjörsbyrå AB and Erik Bernesson, Co-owner, BerDiz Consulting AB | Bulletin N-15-05
“Validated Computational Solutions for Pipe Vibrations and Design Analysis”
L. Andersson, P. Andersson, J. Lundwall, J. Sundqvist, K. Nilsson, P. Veber | Computers & Structures Vol. 81, pp 469-476, 2003, in co-operation with OKG and Ringhals
“On the validation and application of fluid-structure interaction analysis of reactor vessel internals at loss of coolants accidents”
L. Andersson, P. Andersson | Computers & Structures Vol. 64, pp 893-907, 1997
“Some experiences in the use of Adina in the Swedish nuclear industry”
Dr. H. Tinoco | ISBN 978-953-51-0987-7, chapter "CFD as a Tool for the Analysis of the Mechanical Integrity of Light Water Nuclear Reactors"
“Nuclear Reactor Thermal Hydraulics and Other Applications”
“CFD as a Tool for the Analysis of the Mechanical Integrity of Light Water Nuclear Reactors”
Referenced
Presented by Westinghouse Electric Sweden | on the VRD 3rd Nordic Conference on Fluid Dynamics in the Power Industry, 2009, Copenhagen, Denmark
“Analysis of drive housing flow mechanisms following the control rod cracking at Forsmark 3 and Oskarshamn 3”
NEA/CSNI/R(2007)13, Nuclear Energy Agency, 2008
“Assessment of Computational Fluid Dynamics (CFD) for Nuclear Reactor Safety Problems”
Presented
K. Bengtsson | 2016, Energiforsk, Stockholm, Sweden
“FSI-analysis on vibrations of a slender rod exposed to axial flow”
N. Jobert, K. Nilsson, et. al. | in co-operation with AREVA NP, ASME PVP 2010, Bellevue, WA, USA
“Flow-Induced Vibrations: Shortcuts and Pitfalls in Estimating Structural Response to Turbulence”
L. Andersson | Inspecta Kärnteknik 2009, Sollentuna, Sweden
“Tests for Evaluation of Reactor Component Vibrations Based on CFD Loads”
T. Probert and P. Veber | in co-operation with OKG, Inspecta Kärnteknik 2009, Sollentuna, Sweden
“Some Remarks on the Modelling of Main Circulation Loop Breaks in Sweden”
L. Andersson | VRD 3rd Nordic Conference on Fluid Dynamics in the Power Industry, 2009, Copenhagen, Denmark
“Method Development for Prediction of Component Vibrations based on Loads from CFD”
K. Nilsson | TW3, SMiRT 20, 2009, Helsinki, Finland
“Some Experiences from HDR V31.1 and Applied LOCA Analyses on BWR and PWR”
J. Westin, P. Veber, L. Andersson, et. al. al. | ICONE16-48731, 2008, Orlando, Florida, USA. In co-operation with Vattenfall R&D, Forsmark Kraftgrupp and Ringhals.
“High-cycle Thermal Fatigue in Mixing Tees. Large-Eddy Simulations Compared to a new Validation Experiment”
J. Westin, P. Veber, L. Andersson, et. al. al. | ICONE16-48731, 2008, Orlando, Florida, USA. In co-operation with Vattenfall R&D, Forsmark Kraftgrupp and Ringhals.
“High-cycle Thermal Fatigue in Mixing Tees. Large-Eddy Simulations Compared to a new Validation Experiment”
K. Nilsson, L. Andersson | Inspecta Kärnteknik 2008, Arlanda, Sweden
“Some experiences of FSI effects on Pressure Vessels and Piping”
L. Andersson, P. Veber | BWR-OG Workshop on Thermal Stratification 2008, Älvkarleby, Sweden
“CFD simulation of the thermal mixing in the upper plenum and hot leg in a PWR”
F. Tornberg, L. Andersson | Inspecta Kärnteknik 2007, Arlanda, Sweden
“Structural Response from a Pipe Break on the Primary System on a PWR”
K. Nilsson, F. Tornberg, L. Andersson | Inspecta Kärnteknik 2006, Arlanda, Sweden
“Structural Analysis of Ringhals 1 Reactor Pressure Vessel Nozzles”
J. Westin, F. Alavyoon, L. Andersson, P. Veber, M. Henriksson, C. Andersson | OECD/NEA/IAEA Workshop on the Benchmarking of CFD Codes for Application to Nuclear Reactor Safety (CFD4NRS), 2006, Munich, Germany, in co-operation with Vattenfall R&D, Forsmark Kraftgrupp and Ringhals.
“Experiments and Unsteady CFD-Calculations of Thermal Mixing in a T-junction”
P. Veber, L. Andersson | DNV Kärnteknik 2005, Arlanda, Sweden
“Various tests with Large Eddy Simulation turbulence model on Nuclear related problems”
P. Veber, L. Andersson | DNV Kärnteknik 2004, Arlanda, Sweden
“On the Validation and Application of Fluid Structure Interaction Analysis of Reactor Vessel Internals at Loss of Coolant Accidents”
P. Veber, L. Andersson | DNV Kärnteknik 2004, Arlanda, Sweden
“On the Validation and Application of Fluid Structure Interaction Analysis of Reactor Vessel Internals at Loss of Coolant Accidents”
L. Andersson, P. Andersson, J. Lundwall, J. Sundqvist, P. Veber | ASME PVP-Vol. 435, pp 47-62, 2002, in co-operation with OKG and Ringhals.
“Numerical Simulation of the HDR Blowdown Experiment V31.1 at Karlsruhe”
References
Some of the projects in the last 10 years
2011 - Oskarshamn 3
Causal analysis of vibrations on steam lines.
2011-2014 - Ringhals 1
Project STING – Structural verification of reactor tank and internal parts.
2011-2012 - Ringhals 3/4
Complete models of all internal parts in CAD format from drawings.
2012 - Oskarshamn 3
Analysis of flow-induced vibrations in the check valve of the feedwater system during power increase.
2012 - Oskarshamn 1
Flow analysis of the feedwater diffuser and causal analysis of the cracks found.
2012 - Ringhals
Evaluation of turbine blades when a crack is found during an audit.
2012 - Forsmark 2
Structural verification of the bottom region including supports, for all transients and events.
2012-2014 - Ringhals 2
Evaluation of forces on fuel in case of a postulated pipe rupture.
2013-2016 - Ringhals 1
LTO (Long Time Operation) project – Fatigue analysis with environmental factors. Development of environmental impact scripts.
2013-2014 - Ringhals 1
Structural verification of the feedwater segment for 50 years of operation.
2014 -2015 - Ringhals 3
Project PRIO – Structural verification of surge line and spray line. Flow analysis of possible stratification.
2014 - Oskarshamn 3
Analysis of the flow field in the fall gap during coarse level measurement.
2015 - Oskarshamn 1
LTO project (Long Time Operation) – Fatigue analysis of reactor vessel and internal parts for all H1/H2 transients considering environmental factors.
2015 - Ringhals 1
Project STING – LTO project (Long Time Operation) – Structural verification of the reactor vessel and internal parts for all level A/B transients taking into account environmental factors.
2015-2016 - Ringhals 2
Evaluation of forces on fuel in case of a postulated pipe rupture. Structural dynamic verification analysis with two-way FSI as a basis for continued operation.
2016-2017 - Forsmark 1-2
Long Time Operation (LTO) project – Fatigue analysis of the lower reactor vessel and associated penetrations for all level A/B transients taking into account environmental factors.
2017-2020 - Ringhals 3-4
LTO project (Long Time Operation) – Fatigue analysis of main cooling circuits with connecting supports, all level A/B transients considering environmental factors.
2019-2022 - Ringhals 3-4
Pipe breakage analysis.