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Under the NKS-R programme, activities are grouped under the following research areas:

Thermal hydraulics
Severe accidents
Reactor physics
Risk analysis & probabilistic methods
Organisational issues and safety culture
Decommissioning, including decommissioning waste
Plant life management and extension

pdfATR-2 Part B: Ruthenium transport in an RCS with airborne CsI
pdfScenarios and Phenomena Affecting Risk of Containment Failure and Release Characteristics
pdfModelling as a Tool to Augment Ground Motion Data in Regions of Diffuse Seismicity – Final report
pdfModelling of a Large Water Pool during Operation of Blowdown Pipes, Spargers, and Nozzles
pdfSimulation of PPOOLEX stratification and mixing experiment SPA-T1
pdfData and visualization solutions for HYBRID core simulation method
pdfDevelopment of a hybrid neutron transport solver in 2 energy groups
pdfAddressing off-site consequence criteria using Level 3 PSA
pdfBarsebäck as Research and Development Platform, Extraction and Analysis of Reactor Pressure Vessel Material
pdfPreliminary Spray Tests in PPOOLEX
pdfMixing Tests with an RHR Nozzle in PPOOLEX
pdfSparger Tests in PPOOLEX on the Behaviour of Thermocline
pdfSafety Culture Assurance and Improvement Methods in Complex Projects – Intermediate Report from the NKS-R SC_AIM
pdfAddressing off-site consequence criteria using Level 3 PSA - Phase 3 Status Report from the NKS-R L3PSA
pdfEx-Vessel Steam Explosion Analysis with MC3D
pdfA summary of studies on debris bed coolability and multi-dimensional flooding
pdfATR-2 Part A: Ruthenium chemistry and transport in a RCS due to air radiolysis products
pdfExperimental and Analytical Investigations of Debris Bed Formation, Spreading, Coolability, and Steam Explosion in Nordic BWRs
pdfThermal Stratification and Mixing in a Large Pool Induced by Operation of Spargers, Nozzles, and Blowdown Pipes
pdfPre-calculation of a PPOOLEX spray experiment
pdfSingle Spray Nozzle Tests
pdfCFD simulations of preliminary single spray experiments
pdfAdditional Sparger Tests in PPOOLEX with Reduced Number of Injection Holes
pdfModelling as a tool to augment ground motion data in regions of diffuse seismicity - Progress 2015
pdfModelling of DIgital I&C, MODIG — Interim report 2015
pdfSafety Demonstration Planning for Digital I&C Projects – Challenges, Future Directions and Improving Guidance
pdfLearning from Successes in Nuclear Power Plant Operation - Intermediate Report from the NKS-R LESUN
pdfMC3D simulations of ex-vessel steam explosions in IDPSA framework
pdfTreatment of ex-vessel debris coolability in IDPSA context
pdfModelling of the Effects of Steam Injection through Spargers on Pool Thermal Stratification and Mixing
pdfAnalysis of Debris Bed Formation, Spreading, Coolability, and Steam Explosion in Nordic BWRs
pdfDeterministic-Probabilistic Safety Analysis Methodology for Analysis of Core Degradation, Ex-vessel Steam Explosion and Debris Coolability
pdfAnalysing Steam Explosions with MC3D
pdfCoolability analyses of heap-shaped debris bed
pdfSoftware reliability analysis for PSA: failure mode and data analysis
pdfCFD and FEM modeling of blowdown of gas into pressure suppression pool
pdfAddressing off-site consequence criteria using Level 3 PSA
pdfPPOOLEX Experiments with a Sparger
pdfPIV Measurements of DCC-06 and DCC-07 PPOOLEX Experiments
pdfMeasuring Procedure Competence. Final Report from the NKS-R(14)112/13
pdfGuidelines for reliability analysis of digital systems in PSA context — Final report
pdfNordic Nuclear Forum for Generation IV Reactors 2014
pdfHuman performance tools in nuclear power plant maintenance activities - Final report of HUMAX project
pdfPrediction and validation of pool fire development in enclosures by means of CFD Models for risk assessment of nuclear power plants (Poolfire) – Final Report
pdfHuman-Performance Tools in Maintenance Work - A Case Study in a Nordic Nuclear Power Plant
pdfSensitivity Study of Steam Explosion Energetics in Reference Nordic BWR using MC3D Code
pdfStudy and comparison of data on Coolability of Particulate Beds Packed with Irregular Multi-size Particles
pdfAnalysis of Debris Bed Formation, Spreading, Coolability, and Steam Explosion in Nordic BWRs
pdfEffective Models for Simulation of Thermal Stratification and Mixing Induced by Steam Injection into a Large Pool of Water
pdfFeasibility Study for Connection Between IDPSA and conventional PSA Approach to Analysis of Nordic type BWR’s
pdfA study on the coolability of debris bed geometry variations using 2D and 3D models
pdfCOOLOCE-12 debris bed coolability experiment: Cone on a cylindrical base
pdfCOOLOCE debris bed coolability experiments with an agglomerate
pdfChugging Test with DN100 Blowdown Pipe in the PPOOLEX Facility
pdfPPOOLEX Mixing Experiments
pdfCFD and FEM simulations of pressure suppression pool behaviour
pdfEvaluation of Existing Applications and Guidance on Methods for HRA – EXAM-HRA - Phase 3a Summary Report
pdfSoftware reliability analysis for PSA
pdfAddressing off-site consequence criteria using Level 3 PSA — Phase 1 Status Report
pdfGuidelines for reliability analysis of digital systems in PSA context — Phase 4 Status Report
pdfImproving design processes in the nuclear domain. Insights on organisational challenges from safety culture and resilience engineering perspectives
pdfThe expected and experienced benefits of Human performance tools in nuclear power plant maintenance activities - Intermediate report of HUMAX project
pdfNKS-R Decommissioning Seminar 2013
pdfSimulations of Ex-vessel Fuel Coolant Interactions in a Nordic BWR using MC3D Code
pdfStudy on Effective Particle Diameters and Coolability of Particulate Beds Packed with Irregular Multi-size Particles
pdfInvestigation of debris bed formation, spreading and coolability
pdfCOOLOCE debris bed experiments and simulations investigating the coolability of cylindrical beds with different materials and flow modes
pdfAdsorption and revaporisation studies of thin iodine oxide and CsI aerosol deposits from containment surface materials in LWRs
pdfValidation of Effective Momentum and Heat Flux Models for Stratification and Mixing in a Water Pool
pdfModelling of pressure loads in a pressure suppression pool
pdfPrediction and validation of pool fire development in enclosures by means of CFD Models for risk assessment of nuclear power plants (Poolfire) - Report Year 2
pdfPPOOLEX EXPERIMENTS ON THE DYNAMICS OF FREE WATER SURFACE IN THE BLOWDOWN PIPE
pdfPIV MEASUREMENTS AT THE BLOWDOWN PIPE OUTLET
pdfFinal report of MoReMO 2011-2012. Modelling Resilience for Maintenance and Outage
pdfSafety culture in design
pdfGuidelines for reliability analysis of digital systems in PSA context — Phase 3 Status Report
pdfAdsorption and revaporisation studies on iodine oxide aerosols deposited on containment surface materials in LWR
pdfNordic Forum for Generation IV Reactors, Status and activities in 2012
pdfEffective Momentum and Heat Flux Models for Simulation of Stratification and Mixing in a Large Pool of Water
pdfModeling of interaction of multiple vent pipes in a pressure suppression pool
pdfOrganizational factors in design and implementation of technological and organizational solutions in the nuclear industry.
pdfIntermediate report of MoReMO. Modelling Resilience for Maintenance and Outage.
pdfGuidelines for reliability analysis of digital systems in PSA context — Phase 2 status report
pdfPrediction and validation of pool fire development in enclosures by means of CFD (Poolfire) Report – Year 1
pdfNOMAGE4 activities 2011, Part II, Supercritical water loop
pdfNOMAGE4 activities, Part I, Nordic Nuclear Materials Forum for Generation IV Reactors: Status and activites in 2011
pdfNumerical modelling of pressure suppression pools with CFD and FEM codes
pdfDevelopment and Validation of Effective Models for Simulation of Stratification and Mixing Phenomena in a Pool of Water
pdfWire System Ageing Assessment and Condition Monitoring (WASCO)
pdfIn-vessel Coolability and Steam Explosion in Nordic BWRs
pdfExperimental study on iodine chemistry (EXSI) - Containment experiments with methyl iodide
pdfMultiple Blowdown Pipe Experiments with the PPOOLEX Facility
pdfPPOOLEX Experiments on Stratification and Mixing in the Wet Well Pool
pdfNuclear Safety Culture in Finland and Sweden - Developments and Challenges
pdfAutomation strategies in five domains - A comparison of levels of automation, function allocation and visualisation of automatic functions
pdfCFD and FEM modeling of PPOOLEX experiments
pdfPPOOLEX Experiments on Dynamic Loading with Pressure Feedback
pdfPPOOLEX Experiments with Two Parallel Blowdown Pipes
pdfComparison of VNEM to Measured Data from Ringhals Unit 3 (Phase 3)
pdfGuidelines for reliability analysis of digital systems in PSA context - Phase 1 Status Report
pdfHuman 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
pdfHuman 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
pdfModeling of Condensation, Stratification, and Mixing Phenomena in a Pool of Water
pdfGuidance to Risk-Informed Evaluation of Technical Specifications using PSA
pdfExperimental study on iodine chemistry (EXSI) -Containment experiments with methyl iodide
pdfIn-vessel Coolability and Steam Explosion in Nordic BWRs
pdfNordic Nuclear Materials Forum for Generation IV Reactors
pdfSafety Culture in the Finnish and Swedish Nuclear Industries - History and Present
pdfComparison of VNEM to Measured Data from Ringhals Unit 3 IACIP, NKS-R-2008-61
pdfModelling of blowdown of steam in the pressurized PPOOLEX facility
pdfStudies on the effect of flaw detection probability assumptions on risk reduction at inspection
pdfExperimental study on iodine chemistry (EXSI) - Containment experiments with elemental iodine
pdfImproving Accuracy of the Calculation of In-core Power Distributions for Light Water Reactors
pdfStratification issues in the primary system. Review of available validation experiments and State-of the-Art in modelling capabilities (StratRev)
pdfPPOOLEX Experiments on Wall Condensation
pdfPPOOLEX Experiments with a Modified Blowdown Pipe Outlet
pdfPPOOLEX Experiments on Thermal Stratification and Mixing
pdfWire System Ageing Assessment and Condition Monitoring (WASCO)
pdfGOTHIC code simulation of thermal stratification in POOLEX facility
pdfProbabilistic Safety Goals. Phase 3 - Status Report
pdfExtremes temperatures and enthalpy in Finland and Sweden in a changing climate
pdfLevels of Automation and User Control - Evaluation of a Turbine Automation Interface
pdfMORE: Management of Requirements in NPP Modernisation Projects, Final Report
pdfProbabilistic Safety Goals. Phase 2 - Status Report
pdfNPSAG/NKS: Interpretation and Evaluation of the Technical Specification Criteria
pdfLINGUISTIC ANALYSIS OF NPP INSTRUCTIONS
pdfCFD Simulation of Air Discharge Tests in the PPOOLEX Facility
pdfSteam Line Rupture Experiments with the PPOOLEX Test Facility
pdfCharacterizing Experiments of the PPOOLEX Test Facility
pdfInteractions of RuO4(g) with different surfaces in nuclear reactor containments
pdfCost Calculations for Decommissioning and Dismantling of Nuclear Research Facilities
pdfConducting organizational safety reviews ? requirements, methods and experience
pdfMORE: Management of Requirements in NPP Modernisation Projects, Project Report 2007
pdfRADDA - Comparison of results of three ATWS/ATWC scenarios simulated with the help of POLCA-T and S3K/RELAP5
pdfAnalysis of flow fields, temperatures and ruthenium transport in the test facility
pdfEx-Vessel Corium Coolability and Steam Explosion Energetics in Nordic Light Water Reactors
pdfWire System Aging Assessment and Condition Monitoring (WASCO)
pdfEx-Vessel Coolability and Energetics of Steam Explosions in Nordic Light Water Reactors
pdfOrganisational reviews - requirements, methods and experience. Progress report 2006
pdfAnalysis of Loads and Fluid-Structure Interactions in a Condensation Pool
pdfProbabilistic Safety Goals. Phase 1 ? Status and Experiences in Sweden and Finland
pdfAutomation Inflicted Differences on Operator Performance in Nuclear Power Plant Control Rooms
pdfExperiments on the behaviour of ruthenium in air ingress accidents
pdfA Procedure to Generate Input Data of Cyclic Softening and Hardening for FEM Analysis from Constant Strain Amplitude Fatigue Tests in LCF Regime
pdfManagement of Requirements in NPP Modernisation Projects. Project Report 2006
pdfCombined Effects Experiments with the Condensation Pool Test Facility
pdfCost Calculations for Decommissioning and Dismantling of Nuclear Research Facilities, Phase 1
pdfMORE. Management of Requirements in NPP Modernisation Projects. Project Report 2005
pdfNKS-R ExCoolSe Mid-term Report. KTH Severe Accidents Research Relevant to the NKS-ExCoolSe
pdfNordic perspectives on safety management in high reliability organizations: Theory and applications
pdfWire System Aging Assessment and Condition Monitoring (WASCO)
pdfFluid-Structure Interaction Analysis of a Water Pool under Loading Caused by Steam Injection
pdfSimulation and Analysis of Data for Enhancing Low Cycle Fatigue Test Procedures
pdfManagement of change in the nuclear industry - Evidence from maintenance reorganizations
pdfExperiments on the behaviour of ruthenium in air ingress accidents - Progress report
pdfThermal stratification experiments with the condensation pool test rig
pdfWorkshop on decommissioning. (Seminarium om avveckling, Risø, 13-15 september 2005)
pdfTraceability and Communication of Requirements in Digital I&C Systems Development. Final Report.
pdfModeling Goals and Functions of Control and Safety Systems - theoretical foundations and extensions of MFM
pdfCountermeasures and Barriers
pdfEx-Vessel Coolability and Energetics of Steam Explosions in Nordic Light Water Reactors - EXCOOLSE Project Report 2004
pdfCondensation Pool Experiments with Steam Using DN200 Blowdown Pipe
pdfMaintenance culture and management of change. - Intermediate report 2004.
pdfFinal Report of the 'Nordic Thermal-Hydraulic and Safety Network (NOTNET)' - Project.
pdfA summary of the Nordic-group conference on safety management, Lund, Sweden, October 28-29, 2004.
pdfNordic Nuclear Safety Research (NKS) Seminar on Experience
pdfFluid-Structure Interaction Analysis of a Water Pool under Loading Caused by a Condensation-Induced Water Hammer.
pdfTraceability and Communication of Requirements in Digital I&C Systems Development - Project Report 2004.
pdfKnowledge Management in Nordic NPPs. Summary report of the findings from the workshop.
pdfNuclear Seminar on Nuclear Automation, 5-7 April 2004 in Oskarshamn, Sweden
pdfRuthenium Behaviour in Severe Nuclear Accident Conditions - Final Report.
pdfPre-Project on Development and Validation of Melt Behavior in Severe Accidents
pdfContextual assessment of maintenance culture at Olkiluoto and Forsmark.
pdfRisk Informed Decision Making - a Pre-Study.
pdfCCF Model Comparison.
pdfPreliminary condensation pool experiments with steam using DN80 and DN100 blowdown pipes.
pdfNumerical analyses of a water pool under loadings caused by a condensation induced water hammer.
pdfOn safety management and nuclear safety.
pdfRuthenium behaviour in severe nuclear accident conditions - progress report.
pdfTraceability and Communication of Requirements in Digital I&C Systems Development. Project Report 2003.
pdfVALDOR 2003. Values in Decisions On Risk. Proceedings.
pdf3D Analysis Methods - Study and Seminar.
pdfSafety Management: A Frame of Reference for Studies of Nuclear Power. Safety Management and Case Studies from Non-Nuclear Contexts
pdfBarriers, Control and Management. Report from the pilot phase.
pdfThe Possibility and the Effects of a Steam Explosion in the BWR Lower Head on Recriticality of a BWR Core
pdfRecriticality calculation with GENFLO code for the BWR core after steam explosion in the lower head
pdfSystematic Analysis of Dependent Human Errors From the Maintenance History at Finnish NPPs - A Status Report
pdfThe Use of Condition Monitoring Information for Maintenance Planning and Decision-Making
pdfComparative Study of Approaches to Estimate Pipe Break Frequencies
pdfNuclear Safety in Perspective. Final Report of the Nordic Nuclear Safety Research Project SOS-1
pdfStructural integrity of a reinforced concrete structure and a pipe outlet under hydrogen detonation conditions
pdfAdvances in operational safety and severe accident research. Final report of the Nordic Nuclear Safety Research Project SOS-2
pdfA risk informed safety classification for a Nordic NPP
pdfSevere Accident Research and Management in Nordic Countries - A Status Report
pdfA Study on Hydrogen Deflagration for Selected Severe Accident Sequences in Ringhals 3
pdfFormation and behaviour of organic iodine
pdfAn analysis of errors of commission in the Nordic nuclear power plants based on plant operating experience
pdfSafety and Radiation Protection in Waste Management. Final Report of the Nordic Nuclear Safety Research Project SOS-3
pdfRadioactivity in commercially available metals
pdfHuman factors in maintenance: Development and research in Swedish nuclear power plants
pdfIdentification and communication of uncertainties of phenomenological models in PSA
pdfDecision criteria in PSA applications
pdfSyn på kvalitetssäkring vid finländska och svenska kärnkraftverk samt vid Haldenreaktorn
pdfGränsöverskridande kommunikation - Problem och lärdomar i kommunikationen över expertområden
pdfNKS/SOS-1 Seminar on Safety analysis. Report from a seminar held on 22-23 March 2000. Risø National Laboratory, Roskilde, DK
pdfNKS/SOS-1 Seminarium, 2000-09-25 - Riskkommunikation i Oskarshamn
pdfExperiences of Storage of Radioactive Waste Packages in the Nordic Countries
pdfExperience from the comparison of two PSA-studies
pdfOrganisationskulturen 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.
pdfBehandling av säkerhetsrelaterade frågor i kärnkraftverkens ledningsgrupper, (Handling of safety issues in the senior management group at the nuclear power plants)
pdfNKS/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)
pdfThree-dimensional Simulation of Hydrogen Detonations in the Olkiluoto BWR Reactor Building
pdfGas Phase Chemistry and Removal of CH3I during a Severe Accident
pdfSafety- and risk analysis activities in other areas than the nuclear industry
pdfCurrent practice for clearance in the Nordic Countries
pdfReinforced concrete wall under hydrogen detonation
pdfSyn på säkerhetskultur vid svenska och finska kärnkraftverk
pdfOn Detonation Dynamics in Hydrogen-Air-Steam Mixtures: Theory and Application to Olkiluoto Reactor Building
pdfSOS-1 Seminarium om säkerhetskultur. Rapport från ett seminarium i Olkiluoto d. 26-27 oktober 1999
pdfMiljökonsekvensbeskrivningar vid slut-förvaring av radioaktivt avfall. Temamöte, Roskilde, Danmark, 30-31 augusti 1999
pdfFinal Summary Report of the Nordic Nuclear Safety Research Program 1994-1997
pdfMethods to Prevent the source Term of Methyl Iodide During a Core Melt Accident
pdfReliability Centered Maintenance miniseminar
pdfProceedings of the NKS/SOS-2 Seminar on Risk Informed Principles. Bergendal 13.4.-14.4 1999
pdfDescription of the Magnox Type of Gas Cooled Reactor (MAGNOX)
pdfSäkerhetsindikatorer inom kärnkraftindustrin; definitioner, användning och erfarenheter Rapport från ett seminarium på VTT den 17-18 mars 1999
pdfMiljökonsekvensbeskrivningar vid slutförvaring av radioaktivt avfall. Temamöte, Gardermoen, Norge, 24-25 november 1998
pdfSystematisk underhållsanalys med beslutsstöd. Metodik och verktyg för effektivisering av underhållsprogram
pdfA Procedure for Estimation of Pipe Break Probabilities due to IGSCC
pdfREAKTORSÄKERHET; En beskrivning och värdering av säkerhetsarbetet i Norden (see also NKS-76)
pdfModernisation for Maintaining and Improving Safety at Nordic Nuclear Power Plants
pdfIntegrated Sequence Analysis
pdfSource Term Calculations - Ringhals 2 PWR
pdfParametric Studies on Containment Thermal Hydraulic Loads during high pressure Melt Ejection in a BWR
pdfStrategies for Reactor Safety: Preventing Loss of Coolant Accidents
pdfSafety in the Final Disposal of Radioactive Waste
pdfSafety against Releases in Severe Accidents
pdfStrategies for Reactor Safety
pdfCharacterisation of long-lived low and intermediate-level radioactive wastes in the Nordic countries
pdfOn core debris behaviour in the pressure vessel lower head of Nordic boiling water reactors
pdfDescription of Sizewell B Nuclear Power Plant
pdfOn recriticality during reflooding of a degrading boiling water reactor core
pdfPerformance analysis for waste repositories in the Nordic countries - Report for Project AFA-1.2
pdfCAMS Achievements in 1996
pdfSeminarium om Granskning för säkerhet och kvalitet Strategi och praxis. den 16-17 januari 1997 på VTT i Esbo, Finland
pdfDescription of the Advanced Gas Cooled Type of Reactor (AGR)
pdfStudies on melt-water-structure interaction during severe accidents
pdfEn jämförelse mellan myndighetsarbetet inom kärnsäkerheten i Finland och Sverige
pdfA cognitive task analysis of the SGTR scenario
pdfCAMS achievements in 1995
pdfDescription of the Prototype Fast Reactor at Dounreay
pdfAvfallskaraktärisering för långlivat låg- och medelaktivt avfall i Norden - Delrapportering för projekt AFA-1.1
pdfCoolability of degraded core under reflooding conditions in Nordic boiling water reactors
pdfSurvey of methods for integrated sequence analysis with emphasis on man-machine interaction
pdfSummary of approaches to dynamic analysis of man-machine interaction
pdfThe CAMS prototype
pdfNordic studies in reactor safety
pdfSafety Evaluation by Living Probabilistic Safety Asssessment and Safety Indicators
pdfDecommissioning of a Uranium Reprocessing Pilot Plant
pdfDesign and safety features of nuclear reactors neighbouring the Nordic countries
pdfThe Nordic programme on waste and decommisioning (KAN) 1990-93
pdfGuidance on Clearance from Regulatory Control of Radioactive Materials
pdfCleanup of Large Radioactive-contaminated Areas and Disposal of Generated Waste
pdfConservation and Retrieval of Information - Elements of strategy to inform future societies about nuclear waste repositories
pdfDisposal of Radioactive Wastes from the Cleanup of Large Areas Contaminated in Nuclear Accidents - A literature survey
pdfAspects of nuclear waste management after a 4-year Nordic programme
pdfThe influence of chemistry on core melt accidents
pdfOptimization of technical specifications by use of probabilistic methods - A Nordic perspective
pdfNatural radiation, nuclear wastes and chemical pollutants
pdfDependencies, human interactions and uncertainties in probabilistic safety assessment
pdfManagement of radioactive waste from a major core damage in a BWR power plant
pdfSome studies related to decommissioning of nuclear reactors
pdfKvalitetssäkring av transportbehållare för radioaktivt material
pdfGeologifrågor i samband med slutförvar av kärnbränsle i det fennoskandiska urberget
pdfOptimization of radiation protection at nuclear power plants
pdfPrinciples for decisions involving environmental and health risks
pdfRisk analysis and safety rationale
pdfPrevention of catastrophic failure in pressure vessels and pipings
pdfCrack arrest - additional safety against catastrophic fracture
pdfNordiska transporter
pdfIntergranular stress corrosion cracking
pdfSevere accidents analysis - a Nordic study of codes
pdfCorrosion in seawater systems
pdfTraining diagnostic skills for nuclear power plants
pdfNordic Reactor Safety Research 1981 - 85. Summary report of the NKA/SÄK Programme
pdfSjøvannsbestandige materialer - kunnskapsoverføring fra kjernekraft til offshoreindustrien
pdfRisk analysis uses and techniques in the non-nuclear field - a Nordic perspective
pdfEmnesorienterte prosjektkataloger - en katalysator for nordisk samarbeid?
pdfThe human component in the safety of complex systems
pdfManagement of radioactive waste resulting from nuclear fuel damage
pdfOrganization for safety
pdfLong-term properties of bituminized waste products
pdfComputer codes for small-break loss-of-coolant accidents - a Nordic assessment
pdfCorrosion in the nuclear industry - a Nordic survey
pdfThe design process and the use of computerized tools in control room design
pdfComputer aided operation of complex systems - experimental testing and evaluation
pdfHuman errors in test and maintenance in nuclear power plants - Nordic project work
pdfTowards more realistic assessment of reactor accident consequences - A Nordic project
pdfPRA uses and techniques - a Nordic perspective
pdfHeat transfer correlations in nuclear reactor safety calculations - Vol. II
pdfHeat transfer correlations in nuclear reactor safety calculations - Vol. I
pdfEnlarged Nordic Cooperative Program On Nuclear Safety. Nuclide content in reactor waste
pdfNuclide content in reactor waste
pdfEnlarged Nordic Cooperative Program On Nuclear Safety. Nordic study on reactor waste. Technical Part III Product Characteristics
pdfEnlarged Nordic Cooperative Program On Nuclear Safety. Nordic study on reactor waste. Technical Part I Reference System & Technical Part II Safety Analysis
pdfEnlarged Nordic Cooperative Program On Nuclear Safety. Nordic study on reactor waste. Main report
pdfNordic study on reactor waste - Tecnical part I, Reference system - Technical part II, Safety analysis
pdfNordic study on reactor waste - Technical part III, Product Characteristics
pdfNordic study on reactor waste - Main report
pdfTEST
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