References

PUBLISHED:

Jens Conzen, Manager, Structural Services & Vibration, Fauske & Associates, LLC, Pascal Veber, PhD, CEO, Onsala Ingenjörsbyrå AB and Erik Bernesson, Co-owner, BerDiz Consulting AB "Validated Computational Solutions for Pipe Vibrations and Design Analysis" Bulletin N-15-05

L. Andersson, P. Andersson, J. Lundwall, J. Sundqvist, K. Nilsson, P. Veber, "On the validation and application of fluid-structure interaction analysis of reactor vessel internals at loss of coolants accidents", Computers & Structures Vol. 81, pp 469-476, 2003, in co-operation with OKG and Ringhals.

L. Andersson, P. Andersson, "Some experiences in the use of Adina in the Swedish nuclear industry", Computers & Structures Vol. 64, pp 893-907, 1997

Dr. H. Tinoco, "Nuclear Reactor Thermal Hydraulics and Other Applications", ISBN 978-953-51-0987-7, chapter "CFD as a Tool for the Analysis of the Mechanical Integrity of Light Water Nuclear Reactors"

http://www.intechopen.com/articles/show/title/cfd-as-a-tool-for-the-analysis-of-the-mechanical-integrity-of-light-water-nuclear-reactors


REFERENCED:

"Analysis of drive housing flow mechanisms following the control rod cracking at Forsmark 3 and Oskarshamn 3", presented by Westinghouse Electric Sweden on the VRD 3rd Nordic Conference on Fluid Dynamics in the Power Industry, 2009, Copenhagen, Denmark

"Assessment of Computational Fluid Dynamics (CFD) for Nuclear Reactor Safety Problems", NEA/CSNI/R(2007)13, Nuclear Energy Agency, 2008

 

PRESENTED:

K. Bengtsson, "FSI-analysis on vibrations of a slender rod exposed to axial flow", 2016, Energiforsk, Stockholm, Sweden

N. Jobert, K. Nilsson, et. al., "Flow-Induced Vibrations: Shortcuts and Pitfalls in Estimating Structural Response to Turbulence", in co-operation with AREVA NP, ASME PVP 2010, Bellevue, WA, USA

L. Andersson, "Tests for Evaluation of Reactor Component Vibrations Based on CFD Loads", Inspecta Kärnteknik 2009, Sollentuna, Sweden

T. Probert and P. Veber, "Some Remarks on the Modelling of Main Circulation Loop Breaks in Sweden", in co-operation with OKG, Inspecta Kärnteknik 2009, Sollentuna, Sweden

L. Andersson, "Method Development for Prediction of Component Vibrations based on Loads from CFD", VRD 3rd Nordic Conference on Fluid Dynamics in the Power Industry, 2009, Copenhagen, Denmark

K. Nilsson, "Some Experiences from HDR V31.1 and Applied LOCA Analyses on BWR and PWR", TW3, SMiRT 20, 2009, Helsinki, Finland

J. Westin, P. Veber, L. Andersson, et. al. "High-cycle Thermal Fatigue in Mixing Tees. Large-Eddy Simulations Compared to a new Validation Experiment", ICONE16-48731, 2008, Orlando, Florida, USA. In co-operation with Vattenfall R&D, Forsmark Kraftgrupp and Ringhals.

K. Nilsson, L. Andersson, "Some expriences of FSI effects on Pressure Vessels and Piping", Inspecta Kärnteknik 2008, Arlanda, Sweden

L. Andersson, P. Veber, "CFD simulation of the thermal mixing in the upper plenum and hot leg in a PWR", BWR-OG Workshop on Thermal Stratification 2008, Älvkarleby, Sweden

F. Tornberg, L. Andersson, "Structural Response from a Pipe Break on the Primary System on a PWR", Inspecta Kärnteknik 2007, Arlanda, Sweden

K. Nilsson, F. Tornberg, L. Andersson, "Structural Analysis of Ringhals 1 Reactor Pressure Vessel Nozzles", Inspecta Kärnteknik 2006, Arlanda, Sweden

J. Westin, F. Alavyoon, L. Andersson, P. Veber, M. Henriksson, C. Andersson, "Experiments and Unsteady CFD-Calculations of Thermal Mixing in a T-junction", 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.

P. Veber, L. Andersson, "Various tests with Large Eddy Simulation turbulence model on Nuclear related problems", DNV Kärnteknik 2005, Arlanda, Sweden

P. Veber, L. Andersson, "On the Validation and Application of Fluid Structure Interaction Analysis of Reactor Vessel Internals at Loss of Coolant Accidents", DNV Kärnteknik 2004, Arlanda, Sweden

L. Andersson, P. Andersson, J. Lundwall, J. Sundqvist, P. Veber, "Numerical Simulation of the HDR Blowdown Experiment V31.1 at Karlsruhe", ASME PVP-Vol. 435, pp 47-62, 2002, in co-operation with OKG and Ringhals.

 

CONNECTIONS

Ringhals NPP
Oskarshamn NPP
Forsmark NPP

PRO/E
ANSYS/FLUENT
STAR-CCM+
ADINA R&D
ANSA

Vattenfall R&D
GoVirtual

 

 EXAMPLES OF PROJECTS OVER THE LAST 5 YEARS:

  • 2016-today Forsmark 1-2 (BWR) - LTO project (Long Time Operation) - Fatigue evaluation of the RPV (Reactor Pressure Vessel) bottom segment and nozzles for H1/H2 events, including the effects of environmental parameters (oxygen- and sulfur degeneration etc.) on the fatigue life.
  • 2016 - Ringhals 2 (PWR) - Structural dynamic analysis and evaluation of the forces exerted on the fuel bundle due to a postulated severe pipe break or LOCA (Loss Of Coolant Accident). Verification of continuous operating.

 

  • Ringhals 1 (BWR) - Project STING - LTO project (Long Time Operation) – Fatigue evaluation of the RPV (Reactor Pressure Vessel) and internals for level A/B events, including the effects of environmental parameters (oxygen- and sulfur degeneration etc.) on the fatigue life.
  • 2015 – Oskarshamn 1 (BWR) - LTO project (Long Time Operation) – Fatigue evaluation of the RPV (Reactor Pressure Vessel) and internals for H1/H2 events, including the effects of environmental parameters (oxygen- and sulfur degeneration etc.) on the fatigue life.

 

  • 2014 – Oskarshamn 3 (BWR) - Analysis of the flow field in the downcomer to calibrate measurement equipment that monitors the water level.
  • 2014 -2015 – Ringhals 3 (PWR) - Project PRIO - Structural verification of the surge line including the welds and a flow field analysis to determine the system’s sensitivity to an eventual stratification in the surge line.

 

  • 2013-2014 – Ringhals 1 (BWR) - Structural verification of the feed water segments for LTO (Long Time Operation).
  • 2013-2016 – Ringhals 1 (BWR) - LTO-project – Fatigue evaluation of the complete RPV and internals, including environmental degenerating parameters.

 

  • 2012-2014 – Ringhals 2 (PWR) - Evaluation of the forces exerted on the fuel bundle due to a postulated severe pipe break or LOCA (Loss Of Coolant Accident).
  • 2012 – Forsmark 2 (BWR) - Structural verification of the lower part of the RPV, including the internal pump nozzles for all postulated transients and events.
  • 2012 – Ringhals - Evaluation of a crack found in two turbine blades during a check up on the turbines.
  • 2012 – Oskarshamn 1 (BWR) - Flow field analysis of the feed water dispenser due to a discovered crack, assessment of the probable cause for the crack initiation including evaluation of the modifications made to the dispenser before they were implemented.
  • 2012 – Oskarshamn 3 (BWR) - Analysis of flow induced vibrations, during increase in thermal effect, in one of the check valves to the feed water pipes. The root cause was successfully determined.

 

  • 2011-2012 – Ringhals 3/4 (PWR) - Complete CAD models of all the internals, based on blue prints.
  • 2011-2014 – Ringhals 1 (BWR) - Project STING – Structural verification of the RPV and internals.
  • 2011 – Oskarshamn 3 (BWR) - Root cause analysis of steam line vibrations. The cause was successfully determined.

 

  • 2010-2013 – Ringhals 2 (PWR) - Development of methods to measure the eventual vibrations of the internals by measuring the pressure in the lower RPV remotely, during full power.

 

  • 2009-2011 – Oskarshamn 1 (BWR) - Project KIM - Structural verification of the RPV and internals.
  • 2009 – Oskarshamn 1/2/3 (BWR) - Complete RPV and internals in CAD-format from blue prints.
  • 2009 – Oskarshamn 3 (BWR) - Root cause analysis of crack initiation on the control rods. The cause was successfully determined and further cracks avoided.

     

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