Under the NKS-R programme, activities are grouped under the following research areas:
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PPOOLEX EXPERIMENTS ON THE DYNAMICS OF FREE WATER SURFACE IN THE BLOWDOWN PIPE |
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PIV MEASUREMENTS AT THE BLOWDOWN PIPE OUTLET |
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Final report of MoReMO 2011-2012. Modelling Resilience for Maintenance and Outage |
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Safety culture in design |
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Guidelines for reliability analysis of digital systems in PSA context — Phase 3 Status Report |
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Adsorption and revaporisation studies on iodine oxide aerosols deposited on containment surface materials in LWR |
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Nordic Forum for Generation IV Reactors, Status and activities in 2012 |
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Effective Momentum and Heat Flux Models for Simulation of Stratification and Mixing in a Large Pool of Water |
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Modeling of interaction of multiple vent pipes in a pressure suppression pool |
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Organizational factors in design and implementation of technological and organizational solutions in the nuclear industry. |
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Intermediate report of MoReMO. Modelling Resilience for Maintenance and Outage. |
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Guidelines for reliability analysis of digital systems in PSA context — Phase 2 status report |
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Prediction and validation of pool fire development in enclosures by means of CFD (Poolfire) Report – Year 1 |
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NOMAGE4 activities 2011, Part II, Supercritical water loop |
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NOMAGE4 activities, Part I, Nordic Nuclear Materials Forum for Generation IV Reactors: Status and activites in 2011 |
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Numerical modelling of pressure suppression pools with CFD and FEM codes |
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Development and Validation of Effective Models for Simulation of Stratification and Mixing Phenomena in a Pool of Water |
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Wire System Ageing Assessment and Condition Monitoring (WASCO) |
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In-vessel Coolability and Steam Explosion in Nordic BWRs |
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Experimental study on iodine chemistry (EXSI) - Containment experiments with methyl iodide |
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Multiple Blowdown Pipe Experiments with the PPOOLEX Facility |
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PPOOLEX Experiments on Stratification and Mixing in the Wet Well Pool |
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Nuclear Safety Culture in Finland and Sweden - Developments and Challenges |
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Automation strategies in five domains - A comparison of levels of automation, function allocation and visualisation of automatic functions |
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CFD and FEM modeling of PPOOLEX experiments |
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PPOOLEX Experiments on Dynamic Loading with Pressure Feedback |
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PPOOLEX Experiments with Two Parallel Blowdown Pipes |
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Comparison of VNEM to Measured Data from Ringhals Unit 3 (Phase 3) |
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Guidelines for reliability analysis of digital systems in PSA context - Phase 1 Status Report |
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Human Reliability Guidance - How to Increase the Synergies between Human Reliability, Human Factors, and System Design & Engineering. Phase 2: The American Point of View - Insights of How the US Nuclear Industry Works With Human Reliability Analysis |
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Human Reliability Guidance - How to Increase the Synergies between Human Reliability, Human Factors, and System Design & Engineering. Phase 1: The Nordic Point of View - A User Needs Analysis |
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Modeling of Condensation, Stratification, and Mixing Phenomena in a Pool of Water |
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Guidance to Risk-Informed Evaluation of Technical Specifications using PSA |
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Experimental study on iodine chemistry (EXSI) -Containment experiments with methyl iodide |
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In-vessel Coolability and Steam Explosion in Nordic BWRs |
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Nordic Nuclear Materials Forum for Generation IV Reactors |
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Safety Culture in the Finnish and Swedish Nuclear Industries - History and Present |
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Comparison of VNEM to Measured Data from Ringhals Unit 3 IACIP, NKS-R-2008-61 |
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Modelling of blowdown of steam in the pressurized PPOOLEX facility |
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Studies on the effect of flaw detection probability assumptions on risk reduction at inspection |
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Experimental study on iodine chemistry (EXSI) - Containment experiments with elemental iodine |
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Improving Accuracy of the Calculation of In-core Power Distributions for Light Water Reactors |
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Stratification issues in the primary system. Review of available validation experiments and State-of the-Art in modelling capabilities (StratRev) |
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PPOOLEX Experiments on Wall Condensation |
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PPOOLEX Experiments with a Modified Blowdown Pipe Outlet |
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PPOOLEX Experiments on Thermal Stratification and Mixing |
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Wire System Ageing Assessment and Condition Monitoring (WASCO) |
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GOTHIC code simulation of thermal stratification in POOLEX facility |
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Probabilistic Safety Goals. Phase 3 - Status Report |
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Extremes temperatures and enthalpy in Finland and Sweden in a changing climate |
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Levels of Automation and User Control - Evaluation of a Turbine Automation Interface |
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MORE: Management of Requirements in NPP Modernisation Projects, Final Report |
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Probabilistic Safety Goals. Phase 2 - Status Report |
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NPSAG/NKS: Interpretation and Evaluation of the Technical Specification Criteria |
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LINGUISTIC ANALYSIS OF NPP INSTRUCTIONS |
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CFD Simulation of Air Discharge Tests in the PPOOLEX Facility |
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Steam Line Rupture Experiments with the PPOOLEX Test Facility |
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Characterizing Experiments of the PPOOLEX Test Facility |
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Interactions of RuO4(g) with different surfaces in nuclear reactor containments |
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Cost Calculations for Decommissioning and Dismantling of Nuclear Research Facilities |
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Conducting organizational safety reviews ? requirements, methods and experience |
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MORE: Management of Requirements in NPP Modernisation Projects, Project Report 2007 |
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RADDA - Comparison of results of three ATWS/ATWC scenarios simulated with the help of POLCA-T and S3K/RELAP5 |
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Analysis of flow fields, temperatures and ruthenium transport in the test facility |
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Ex-Vessel Corium Coolability and Steam Explosion Energetics in Nordic Light Water Reactors |
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Wire System Aging Assessment and Condition Monitoring (WASCO) |
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Ex-Vessel Coolability and Energetics of Steam Explosions in Nordic Light Water Reactors |
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Organisational reviews - requirements, methods and experience. Progress report 2006 |
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Analysis of Loads and Fluid-Structure Interactions in a Condensation Pool |
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Probabilistic Safety Goals. Phase 1 ? Status and Experiences in Sweden and Finland |
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Automation Inflicted Differences on Operator Performance in Nuclear Power Plant Control Rooms |
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Experiments on the behaviour of ruthenium in air ingress accidents |
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A Procedure to Generate Input Data of Cyclic Softening and Hardening for FEM Analysis from Constant Strain Amplitude Fatigue Tests in LCF Regime |
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Management of Requirements in NPP Modernisation Projects. Project Report 2006 |
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Combined Effects Experiments with the Condensation Pool Test Facility |
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Cost Calculations for Decommissioning and Dismantling of Nuclear Research Facilities, Phase 1 |
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MORE. Management of Requirements in NPP Modernisation Projects. Project Report 2005 |
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NKS-R ExCoolSe Mid-term Report. KTH Severe Accidents Research Relevant to the NKS-ExCoolSe |
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Nordic perspectives on safety management in high reliability organizations: Theory and applications |
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Wire System Aging Assessment and Condition Monitoring (WASCO) |
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Fluid-Structure Interaction Analysis of a Water Pool under Loading Caused by Steam Injection |
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Simulation and Analysis of Data for Enhancing Low Cycle Fatigue Test Procedures |
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Management of change in the nuclear industry - Evidence from maintenance reorganizations |
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Experiments on the behaviour of ruthenium in air ingress accidents - Progress report |
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Thermal stratification experiments with the condensation pool test rig |
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Workshop on decommissioning. (Seminarium om avveckling, Risø, 13-15 september 2005) |
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Traceability and Communication of Requirements in Digital I&C Systems Development. Final Report. |
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Modeling Goals and Functions of Control and Safety Systems - theoretical foundations and extensions of MFM |
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Countermeasures and Barriers |
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Ex-Vessel Coolability and Energetics of Steam Explosions in Nordic Light Water Reactors - EXCOOLSE Project Report 2004 |
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Condensation Pool Experiments with Steam Using DN200 Blowdown Pipe |
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Maintenance culture and management of change. - Intermediate report 2004. |
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Final Report of the 'Nordic Thermal-Hydraulic and Safety Network (NOTNET)' - Project. |
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A summary of the Nordic-group conference on safety management, Lund, Sweden, October 28-29, 2004. |
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Nordic Nuclear Safety Research (NKS) Seminar on Experience |
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Fluid-Structure Interaction Analysis of a Water Pool under Loading Caused by a Condensation-Induced Water Hammer. |
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Traceability and Communication of Requirements in Digital I&C Systems Development - Project Report 2004. |
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Knowledge Management in Nordic NPPs. Summary report of the findings from the workshop. |
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Nuclear Seminar on Nuclear Automation, 5-7 April 2004 in Oskarshamn, Sweden |
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Ruthenium Behaviour in Severe Nuclear Accident Conditions - Final Report. |
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Pre-Project on Development and Validation of Melt Behavior in Severe Accidents |
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Contextual assessment of maintenance culture at Olkiluoto and Forsmark. |
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Risk Informed Decision Making - a Pre-Study. |
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CCF Model Comparison. |
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Preliminary condensation pool experiments with steam using DN80 and DN100 blowdown pipes. |
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Numerical analyses of a water pool under loadings caused by a condensation induced water hammer. |
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On safety management and nuclear safety. |
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Ruthenium behaviour in severe nuclear accident conditions - progress report. |
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Traceability and Communication of Requirements in Digital I&C Systems Development. Project Report 2003. |
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VALDOR 2003. Values in Decisions On Risk. Proceedings. |
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3D Analysis Methods - Study and Seminar. |
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Safety Management: A Frame of Reference for Studies of Nuclear Power. Safety Management and Case Studies from Non-Nuclear Contexts |
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Barriers, Control and Management. Report from the pilot phase. |
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The Possibility and the Effects of a Steam Explosion in the BWR Lower Head on Recriticality of a BWR Core |
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Recriticality calculation with GENFLO code for the BWR core after steam explosion in the lower head |
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Systematic Analysis of Dependent Human Errors From the Maintenance History at Finnish NPPs - A Status Report |
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The Use of Condition Monitoring Information for Maintenance Planning and Decision-Making |
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Comparative Study of Approaches to Estimate Pipe Break Frequencies |
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Nuclear Safety in Perspective. Final Report of the Nordic Nuclear Safety Research Project SOS-1 |
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Structural integrity of a reinforced concrete structure and a pipe outlet under hydrogen detonation conditions |
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Advances in operational safety and severe accident research. Final report of the Nordic Nuclear Safety Research Project SOS-2 |
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A risk informed safety classification for a Nordic NPP |
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Severe Accident Research and Management in Nordic Countries - A Status Report |
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A Study on Hydrogen Deflagration for Selected Severe Accident Sequences in Ringhals 3 |
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Formation and behaviour of organic iodine |
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An analysis of errors of commission in the Nordic nuclear power plants based on plant operating experience |
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Safety and Radiation Protection in Waste Management. Final Report of the Nordic Nuclear Safety Research Project SOS-3 |
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Radioactivity in commercially available metals |
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Human factors in maintenance: Development and research in Swedish nuclear power plants |
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Identification and communication of uncertainties of phenomenological models in PSA |
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Decision criteria in PSA applications |
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Syn på kvalitetssäkring vid finländska och svenska kärnkraftverk samt vid Haldenreaktorn |
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Gränsöverskridande kommunikation - Problem och lärdomar i kommunikationen över expertområden |
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NKS/SOS-1 Seminar on Safety analysis. Report from a seminar held on 22-23 March 2000. Risø National Laboratory, Roskilde, DK |
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NKS/SOS-1 Seminarium, 2000-09-25 - Riskkommunikation i Oskarshamn |
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Experiences of Storage of Radioactive Waste Packages in the Nordic Countries |
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Experience from the comparison of two PSA-studies |
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Organisationskulturen inom den finländska Strålsäkerhetscentralens (STUK) avdelning för övervakning av kärnkraftverk. Organisational culture at the Radiation and Nuclear Safety Authority of Finland's department of Nuclear Reactor Regulation. |
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Behandling av säkerhetsrelaterade frågor i kärnkraftverkens ledningsgrupper, (Handling of safety issues in the senior management group at the nuclear power plants) |
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NKS/SOS-1 Seminarium om Kvalitetssäkring. Rapport från ett seminarium i Ringhals den 16-17 januari 2001. (NKS/SOS-1 Seminar on Quality Assurance in Nordic nuclear reactor plants. Ringhals, January 16-17, 2001) |
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Three-dimensional Simulation of Hydrogen Detonations in the Olkiluoto BWR Reactor Building |
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Gas Phase Chemistry and Removal of CH3I during a Severe Accident |
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Safety- and risk analysis activities in other areas than the nuclear industry |
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Current practice for clearance in the Nordic Countries |
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Reinforced concrete wall under hydrogen detonation |
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Syn på säkerhetskultur vid svenska och finska kärnkraftverk |
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On Detonation Dynamics in Hydrogen-Air-Steam Mixtures: Theory and Application to Olkiluoto Reactor Building |
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SOS-1 Seminarium om säkerhetskultur. Rapport från ett seminarium i Olkiluoto d. 26-27 oktober 1999 |
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Miljökonsekvensbeskrivningar vid slut-förvaring av radioaktivt avfall. Temamöte, Roskilde, Danmark, 30-31 augusti 1999 |
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Final Summary Report of the Nordic Nuclear Safety Research Program 1994-1997 |
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Methods to Prevent the source Term of Methyl Iodide During a Core Melt Accident |
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Reliability Centered Maintenance miniseminar |
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Proceedings of the NKS/SOS-2 Seminar on Risk Informed Principles. Bergendal 13.4.-14.4 1999 |
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Description of the Magnox Type of Gas Cooled Reactor (MAGNOX) |
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Säkerhetsindikatorer inom kärnkraftindustrin; definitioner, användning och erfarenheter Rapport från ett seminarium på VTT den 17-18 mars 1999 |
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Miljökonsekvensbeskrivningar vid slutförvaring av radioaktivt avfall. Temamöte, Gardermoen, Norge, 24-25 november 1998 |
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Systematisk underhållsanalys med beslutsstöd. Metodik och verktyg för effektivisering av underhållsprogram |
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A Procedure for Estimation of Pipe Break Probabilities due to IGSCC |
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REAKTORSÄKERHET; En beskrivning och värdering av säkerhetsarbetet i Norden (see also NKS-76) |
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Modernisation for Maintaining and Improving Safety at Nordic Nuclear Power Plants |
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Integrated Sequence Analysis |
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Source Term Calculations - Ringhals 2 PWR |
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Parametric Studies on Containment Thermal Hydraulic Loads during high pressure Melt Ejection in a BWR |
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Strategies for Reactor Safety: Preventing Loss of Coolant Accidents |
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Safety in the Final Disposal of Radioactive Waste |
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Safety against Releases in Severe Accidents |
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Strategies for Reactor Safety |
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Characterisation of long-lived low and intermediate-level radioactive wastes in the Nordic countries |
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On core debris behaviour in the pressure vessel lower head of Nordic boiling water reactors |
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Description of Sizewell B Nuclear Power Plant |
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On recriticality during reflooding of a degrading boiling water reactor core |
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Performance analysis for waste repositories in the Nordic countries - Report for Project AFA-1.2 |
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CAMS Achievements in 1996 |
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Seminarium om Granskning för säkerhet och kvalitet Strategi och praxis. den 16-17 januari 1997 på VTT i Esbo, Finland |
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Description of the Advanced Gas Cooled Type of Reactor (AGR) |
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Studies on melt-water-structure interaction during severe accidents |
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En jämförelse mellan myndighetsarbetet inom kärnsäkerheten i Finland och Sverige |
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A cognitive task analysis of the SGTR scenario |
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CAMS achievements in 1995 |
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Description of the Prototype Fast Reactor at Dounreay |
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Avfallskaraktärisering för långlivat låg- och medelaktivt avfall i Norden - Delrapportering för projekt AFA-1.1 |
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Coolability of degraded core under reflooding conditions in Nordic boiling water reactors |
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Survey of methods for integrated sequence analysis with emphasis on man-machine interaction |
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Summary of approaches to dynamic analysis of man-machine interaction |
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The CAMS prototype |
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Nordic studies in reactor safety |
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Safety Evaluation by Living Probabilistic Safety Asssessment and Safety Indicators |
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Decommissioning of a Uranium Reprocessing Pilot Plant |
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Design and safety features of nuclear reactors neighbouring the Nordic countries |
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The Nordic programme on waste and decommisioning (KAN) 1990-93 |
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Guidance on Clearance from Regulatory Control of Radioactive Materials |
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Cleanup of Large Radioactive-contaminated Areas and Disposal of Generated Waste |
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Conservation and Retrieval of Information - Elements of strategy to inform future societies about nuclear waste repositories |
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Disposal of Radioactive Wastes from the Cleanup of Large Areas Contaminated in Nuclear Accidents - A literature survey |
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Aspects of nuclear waste management after a 4-year Nordic programme |
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The influence of chemistry on core melt accidents |
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Optimization of technical specifications by use of probabilistic methods - A Nordic perspective |
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Natural radiation, nuclear wastes and chemical pollutants |
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Dependencies, human interactions and uncertainties in probabilistic safety assessment |
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Management of radioactive waste from a major core damage in a BWR power plant |
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Some studies related to decommissioning of nuclear reactors |
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Kvalitetssäkring av transportbehållare för radioaktivt material |
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Geologifrågor i samband med slutförvar av kärnbränsle i det fennoskandiska urberget |
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Optimization of radiation protection at nuclear power plants |
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Principles for decisions involving environmental and health risks |
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Risk analysis and safety rationale |
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Prevention of catastrophic failure in pressure vessels and pipings |
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Crack arrest - additional safety against catastrophic fracture |
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Nordiska transporter |
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Intergranular stress corrosion cracking |
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Severe accidents analysis - a Nordic study of codes |
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Corrosion in seawater systems |
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Training diagnostic skills for nuclear power plants |
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Nordic Reactor Safety Research 1981 - 85. Summary report of the NKA/SÄK Programme |
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Sjøvannsbestandige materialer - kunnskapsoverføring fra kjernekraft til offshoreindustrien |
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Risk analysis uses and techniques in the non-nuclear field - a Nordic perspective |
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Emnesorienterte prosjektkataloger - en katalysator for nordisk samarbeid? |
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The human component in the safety of complex systems |
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Management of radioactive waste resulting from nuclear fuel damage |
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Organization for safety |
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Long-term properties of bituminized waste products |
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Computer codes for small-break loss-of-coolant accidents - a Nordic assessment |
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Corrosion in the nuclear industry - a Nordic survey |
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The design process and the use of computerized tools in control room design |
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Computer aided operation of complex systems - experimental testing and evaluation |
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Human errors in test and maintenance in nuclear power plants - Nordic project work |
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Towards more realistic assessment of reactor accident consequences - A Nordic project |
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PRA uses and techniques - a Nordic perspective |
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Heat transfer correlations in nuclear reactor safety calculations - Vol. II |
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Heat transfer correlations in nuclear reactor safety calculations - Vol. I |
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Enlarged Nordic Cooperative Program On Nuclear Safety. Nuclide content in reactor waste |
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Nuclide content in reactor waste |
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Enlarged Nordic Cooperative Program On Nuclear Safety. Nordic study on reactor waste. Technical Part III Product Characteristics |
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Enlarged Nordic Cooperative Program On Nuclear Safety. Nordic study on reactor waste. Technical Part I Reference System & Technical Part II Safety Analysis |
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Enlarged Nordic Cooperative Program On Nuclear Safety. Nordic study on reactor waste. Main report |
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Nordic study on reactor waste - Tecnical part I, Reference system - Technical part II, Safety analysis |
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Nordic study on reactor waste - Technical part III, Product Characteristics |
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Nordic study on reactor waste - Main report |
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NKS Reports 