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Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant
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Mechanistic modelling of station blackout accidents for a generic 900 MW CANDU plant using the modified RELAP/SCDAPSIM/MOD3.6 code Mechanistic modelling of station blackout accidents for a generic 900 MW CANDU plant using the modified RELAP/SCDAPSIM/MOD3.6 code
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Transmutation considerations of LWR and RBMK spent nuclear fuel by the fusion–fission hybrid system Transmutation considerations of LWR and RBMK spent nuclear fuel by the fusion–fission hybrid system
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Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations
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Integrating quantitative defense-in-depth metrics into new reactor designs Integrating quantitative defense-in-depth metrics into new reactor designs
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LDA measurements of coherent flow structures and cross-flow across the gap of a compound channel with two half-rods LDA measurements of coherent flow structures and cross-flow across the gap of a compound channel with two half-rods
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Nuclear energy system’s behavior and decision making using machine learning Nuclear energy system’s behavior and decision making using machine learning
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Development and verification of wall-flap-gate as tsunami inundation defence for nuclear plants Development and verification of wall-flap-gate as tsunami inundation defence for nuclear plants
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Benchmarking LES with wall-functions and RANS for fatigue problems in thermal–hydraulics systems Benchmarking LES with wall-functions and RANS for fatigue problems in thermal–hydraulics systems
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Analysis of flammability in the attached buildings to containment under severe accident conditions Analysis of flammability in the attached buildings to containment under severe accident conditions
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Analysis of loss of offsite power events reported in nuclear power plants Analysis of loss of offsite power events reported in nuclear power plants
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Large eddy simulation of a buoyancy-aided flow in a non-uniform channel – Buoyancy effects on large flow structures Large eddy simulation of a buoyancy-aided flow in a non-uniform channel – Buoyancy effects on large flow structures
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Coupled 3D neutron kinetics and thermalhydraulic characteristics of the Canadian supercritical water reactor Coupled 3D neutron kinetics and thermalhydraulic characteristics of the Canadian supercritical water reactor
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Mechanical performance of integrally bonded copper coatings for the long term disposal of used nuclear fuel Mechanical performance of integrally bonded copper coatings for the long term disposal of used nuclear fuel
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CANDU-6 fuel optimization for advanced cycles CANDU-6 fuel optimization for advanced cycles
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A fission matrix based validation protocol for computed power distributions in the advanced test reactor A fission matrix based validation protocol for computed power distributions in the advanced test reactor
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Concept and methodology for evaluating core damage frequency considering failure correlation at multi units and sites and its application Concept and methodology for evaluating core damage frequency considering failure correlation at multi units and sites and its application
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Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3 Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3
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Density stratification breakup by a vertical jet: Experimental and numerical investigation on the effect of dynamic change of turbulent schmidt number Density stratification breakup by a vertical jet: Experimental and numerical investigation on the effect of dynamic change of turbulent schmidt number
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Preliminary forensic engineering study on aggravation of radioactive releases during the Fukushima Daiichi accident Preliminary forensic engineering study on aggravation of radioactive releases during the Fukushima Daiichi accident
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