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pdfSource Term and Timing Uncertainty in Severe accidents NKS-STATUS Phase 2 report
pdfOrganic Telluride Formation during a Severe Nuclear Accident (ORTEF)
pdfSource Term And Timing Uncertainty in Severe Accidents
pdfScenarios and Phenomena Affecting Risk of Containment Failure and Release Characteristics
pdfMain Outcomes of the TETRA Project on Tellurium Chemistry in a Severe Accident
pdfScenarios and Phenomena Affecting Risk of Containment Failure and Release Characteristics
pdfPhenomena Threatening Containment Integrity in Deterministic and Probabilistic analyses and integration of PRA levels 1 and 2
pdfScenarios and Phenomena Affecting Risk of Containment Failure and Release Characteristics
pdfPhenomena Threatening Containment Integrity and Evaluating Source Term Characteristics
pdfATR-2 Part B: Ruthenium transport in an RCS with airborne CsI
pdfScenarios and Phenomena Affecting Risk of Containment Failure and Release Characteristics
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
pdfAnalysis of Debris Bed Formation, Spreading, Coolability, and Steam Explosion in Nordic BWRs
pdfAnalysing Steam Explosions with MC3D
pdfCoolability analyses of heap-shaped debris bed
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
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
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
pdfAdsorption and revaporisation studies on iodine oxide aerosols deposited on containment surface materials in LWR
pdfIn-vessel Coolability and Steam Explosion in Nordic BWRs
pdfExperimental study on iodine chemistry (EXSI) - Containment experiments with methyl iodide
pdfExperimental study on iodine chemistry (EXSI) -Containment experiments with methyl iodide
pdfIn-vessel Coolability and Steam Explosion in Nordic BWRs
pdfExperimental study on iodine chemistry (EXSI) - Containment experiments with elemental iodine
pdfInteractions of RuO4(g) with different surfaces in nuclear reactor containments
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
pdfEx-Vessel Coolability and Energetics of Steam Explosions in Nordic Light Water Reactors
pdfExperiments on the behaviour of ruthenium in air ingress accidents
pdfNKS-R ExCoolSe Mid-term Report. KTH Severe Accidents Research Relevant to the NKS-ExCoolSe
pdfExperiments on the behaviour of ruthenium in air ingress accidents - Progress report
pdfEx-Vessel Coolability and Energetics of Steam Explosions in Nordic Light Water Reactors - EXCOOLSE Project Report 2004
pdfRuthenium Behaviour in Severe Nuclear Accident Conditions - Final Report.
pdfPre-Project on Development and Validation of Melt Behavior in Severe Accidents
pdfRuthenium behaviour in severe nuclear accident conditions - progress report.
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
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
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
pdfThree-dimensional Simulation of Hydrogen Detonations in the Olkiluoto BWR Reactor Building
pdfGas Phase Chemistry and Removal of CH3I during a Severe Accident
pdfReinforced concrete wall under hydrogen detonation
pdfOn Detonation Dynamics in Hydrogen-Air-Steam Mixtures: Theory and Application to Olkiluoto Reactor Building
pdfMethods to Prevent the source Term of Methyl Iodide During a Core Melt Accident
pdfDescription of the Magnox Type of Gas Cooled Reactor (MAGNOX)
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 against Releases in Severe Accidents
pdfStrategies for Reactor Safety
pdfOn core debris behaviour in the pressure vessel lower head of Nordic boiling water reactors
pdfOn recriticality during reflooding of a degrading boiling water reactor core
pdfStudies on melt-water-structure interaction during severe accidents
pdfDescription of the Prototype Fast Reactor at Dounreay
pdfCoolability of degraded core under reflooding conditions in Nordic boiling water reactors
pdfNordic studies in reactor safety
pdfDesign and safety features of nuclear reactors neighbouring the Nordic countries
pdfThe influence of chemistry on core melt accidents
pdfPrevention of catastrophic failure in pressure vessels and pipings
pdfSevere accidents analysis - a Nordic study of codes
pdfNordic Reactor Safety Research 1981 - 85. Summary report of the NKA/SÄK Programme
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