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Daneshyari Safety, Risk, Reliability and Quality Journas Latest Articles

Safety, Risk, Reliability and Quality Research Articles

Comparison of advanced fast reactor pool and loop configurations from the viewpoint of construction cost
Fulltext Access 8 Pages 2011
Closure of the concrete supercontainer in hot cell under thermal load
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Comparison of two numerical modelling codes for hydraulic and transport calculations in the near-field
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Modelling of Zry-4 cladding oxidation by air, under severe accident conditions using the MAAP4 code
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Sensitivity analysis of the MASLWR helical coil steam generator using TRACE
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Simulation of containment thermal-hydraulics in the Marviken Blowdown 16 experiment with ASTEC and CONTAIN codes
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ASTEC and ICARE/CATHARE modelling improvement for VVERs
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Influence of air entrainment on the liquid flow field caused by a plunging jet and consequences for fibre deposition
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Anomalies and other concerns related to the critical heat flux
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Fluid structure interaction between rods and a cross flow – Numerical approach
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CATHARE 2 V2.5_2: A single version for various applications
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CFD modeling and thermal-hydraulic analysis for the passive decay heat removal of a sodium-cooled fast reactor
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Fluid-to-fluid modeling of two-phase flow critical heat flux in horizontal helically coiled tubes
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Load cell monitoring in Gas Centrifuge Enrichment Plants: Potentialities for improved safeguard verifications
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New fuel rod design based on LEU/Th fuel and an assessment on in-core fuel cycle length of the MHR core
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A diagnostic system for identifying accident conditions in a nuclear reactor
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Modelling heat transfer and dissolved species concentrations within PWR crud
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A possibility of miniaturized fusion and fission hybrid reaction core with positive fusion yield
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Solidification of borate radioactive resins using sulfoaluminate cement blending with zeolite
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Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code
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Reactor cavity cooling system (Rccs) experimental characterization
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Correlations for predicting single phase and two-phase flow pressure drop in pebble bed flow channels
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Selective separation and recovery of cesium by ammonium tungstophosphate-alginate microcapsules
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An evaluation of a direct cooling method for the ex-vessel corium stabilization
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A fuel performance analysis for a 450 MWth deep burn-high temperature reactor
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On the significance of modeling nuclear fuel behavior with the right representation of physical phenomena
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Pu-breeding feasibility in irradiation channels of research reactors
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On the speed of response of an FPGA-based shutdown system in CANDU nuclear power plants
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Analysis of an ADS spurious opening event at a BWR/6 by means of the TRACE code
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An experimental investigation on bending stiffness and neutral axis depth variation of over-reinforced high strength concrete beams
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Critical strains and necking phenomena for different steel sheet specimens under uniaxial loading
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Study on modal characteristics of perforated shell using effective Young's modulus
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A probabilistic seismic risk assessment procedure for nuclear power plants: (I) Methodology
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Severe accident management strategy verification for VVER-1000 (V320) reactor
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A droplet entrainment model based on the force balance of an interfacial wave in two-phase annular flow
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A containment analysis for SBLOCA in the refurbished Wolsong-1 Nuclear Power Plant
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Experimental observation of the droplet size change across a wet grid spacer in a 6 × 6 rod bundle
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Influence of pump starting times on transient flows in pipes
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Extending image processing strain measurement system to evaluate fracture behavior of wall-thinned pipes
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Nuclear and Radiological Emergency Management and Rehabilitation Strategies: Towards a EU approach for decision support tools
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An Abstraction Hierarchy based mobile PC display design in NPP maintenance considering the level of expertise
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Water level control for a nuclear steam generator
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Addressing the challenges posed by advanced reactor passive safety system performance assessment
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Reliability analysis of nuclear component cooling water system using semi-Markov process model
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Pressurized water reactor (PWR) hot-leg streaming: Part 1: Computational fluid dynamics (CFD) simulations
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Flow-induced vibration of nuclear steam generator U-tubes in two-phase flow
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Some insights into the role of axial gas flow in fuel rod behaviour during the LOCA based on Halden tests and calculations with the FALCON-PSI code
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Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPR™: CFD investigations and comparison with experimental results
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Letter to the Editor on the paper by W. Wulff, “Critical review of conservation equations for two-phase flow in the U.S. NRC TRACE Code”
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Cladding rupture life control methods for a power-cycling WWER-1000 nuclear unit
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A decision-analysis approach for optimal airport security
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Periodic large scale vortex structure in rectangular channels with non-uniform wall roughness
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Scaling the transport of firebrands by wind-blown plumes
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Experimental investigation of in-vessel mixing phenomena in a VVER-1000 scaled test facility during unsteady asymmetric transients
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Verification of the accuracy of CFD simulations in small-scale tunnel and atrium fire configurations
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Stratified flow-induced air-ingress accident assessment of the GAMMA code in HTGRs
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Single event upset mitigation techniques for FPGAs utilized in nuclear power plant digital instrumentation and control
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Experimental qualification of subassembly design for Prototype Fast Breeder Reactor
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The effect of post-fire-curing on strength–velocity relationship for nondestructive assessment of fire-damaged concrete strength
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Durability and service life prediction of GFRP bars embedded in concrete under acid environment
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An experimental study on fretting wear behavior of cross-contacting Inconel 690 tubes
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Video-based smoke detection with histogram sequence of LBP and LBPV pyramids
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Damping-controlled fluidelastic instability forces in multi-span tubes with loose supports
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Numerical simulations of the phase separation properties for the thermal aged CDSS with Phase Field Model
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Modelling of light extinction by soot particles
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Experimental study of debris head loss through a pressurized water reactor recirculation sump screen after LOCA
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Effects of non-uniform inlet boundary conditions and lift force on prediction of phase distribution in upward bubbly flows with Fluent-IATE
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A simplified model for nonlinear seismic response analysis of equipment cabinets in nuclear power plants
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On the relevance of low side flows for thermal loads in T-junctions
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SCWR single channel stability analysis using a response matrix method
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Numerical study on thermo-hydrodynamics in the reactor internals of SMART
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Safety assessment of pipes with multiple local wall thinning defects under pressure and bending moment
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Estimation of fracture toughness of 20MnMoNi55 steel in the ductile to brittle transition region using master curve method
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Optimized thick-wall cylinders by virtue of Poisson's ratio selection: Part 1: Isochoric pressure application
Fulltext Access 9 Pages 2011
Capacity reduction and fire load factors for LRFD of steel columns exposed to fire
Fulltext Access 9 Pages 2011
A signaling framework to deter aggression in cyberspace
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Determining hazard risk indices for Mediterranean forest species based on particle flammability properties
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Buckling of timber columns exposed to fire
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An experimental study of the rate of gas temperature rise in enclosure fires
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An integrated methodology to predict the likelihood of spurious actuation of AC circuits due to fires in commercial nuclear power plants
Fulltext Access 9 Pages 2011
Experimental study on the performance of a load-bearing steel stud gypsum board wall assembly exposed to a real fire
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Optimal artificial neural network architecture selection for performance prediction of compact heat exchanger with the EBaLM-OTR technique
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Preliminary conceptual design of a geological disposal system for high-level wastes from the pyroprocessing of PWR spent fuels
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A simple novel analysis procedure for IVR calculation in core-molten severe accident
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Quantification of fire gases by FTIR: Experimental characterisation of calibration systems
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Undesirable flow behavior in a proposed validation data set
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Neutron radiography, a powerful method to determine time-dependent moisture distributions in concrete
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The quenching behavior of aqueous nanofluids around rods with high temperature
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Mechanical properties of steel fiber reinforced reactive powder concrete following exposure to high temperature reaching 800 °C
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Demonstrative testing of honeycomb passive autocatalytic recombiner for nuclear power plant
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Description and preliminary results of PHENIX core flowering test
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Accident testing of high-temperature reactor fuel elements from the HFR-EU1bis irradiation
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CFD simulation of particle deposition on an array of spheres using an Euler/Lagrange approach
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On-line reconstruction of in-core power distribution by harmonics expansion method
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Lead Coolant Test Facility—Design concept and requirements
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A new method to predict Grid-To-Rod Fretting in a PWR fuel assembly inlet region
Fulltext Access 9 Pages 2011
Development and overall testing of the traditional MTC estimation based on noise diagnostics at all four units of the Paks NPP
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A population balance approach considering heat and mass transfer—Experiments and CFD simulations
Fulltext Access 9 Pages 2011
Experimental studies on single-phase flow and heat transfer in a narrow rectangular channel
Fulltext Access 9 Pages 2011
A new mechanistic code SFPR for modeling of single fuel rod performance under various regimes of LWR operation
Fulltext Access 9 Pages 2011
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