Applications of artificial intelligence (AI) technologies for supercritical water reactor (SCWR) and thermal hydraulic modeling of SCWR using deep learning

P. 265-277

• Chapitres du même volume (disponibles individuellement)

  • 25 years of supercritical water-cooled reactor research in Europe : lessons learned and future challenges
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  • Current status of nuclear-power industry of the world
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  • Bridging research and education : the role of the European Nuclear Education Network (ENEN) in building the synergy between Euratom projects
    Obtenir le chapitre
  • A brief review of professor Jackson's contributions to the research of heat transfer to fluids at supercritical pressure
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  • Wall roughness design for supercritical flows
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  • Exploring similarity theories for heat transfer at supercritical pressures : computational insights and experimental implications
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  • Modelling supercritical heat transfer using a two fluid approach
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  • Experimental and machine learning study on mixed convection heat transfer to supercritical pressure CO2 under coupled buoyancy and flow acceleration effects
    Obtenir le chapitre
  • Design concept of a super pressurized water reactor
    Obtenir le chapitre
  • Design and analysis of a reactor pressure vessel for the super pressurized water reactor
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  • Core design of the small super-fast reactor to reduce debris criticality
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  • Progress on a pre-conceptual supercritical water-cooled small modular reactor
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  • Implementation of the ECC-SMART : joint European Canadian Chinese development of small modular reactor technology
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  • Coupling of Apros and SPNDYN to analyse the SCW-SMR concept within ECC-SMART
    Obtenir le chapitre
  • Hybrid finite element SPN analysis of an SCW-SMR concept within the ECC-SMART project
    Obtenir le chapitre
  • Multiphysics assessment of the SCW SMR heat generating channel condition using differential method of the heat transfer intensity and resistance calculation
    Obtenir le chapitre
  • Neutronic analysis of micro-heterogeneous duplex ThO2 -PuO2 fuel pin with burnup characteristics for PT-SCWR
    Obtenir le chapitre
  • A vision for super critical water-cooled reactors : an opinion paper
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  • R&D platform for the SCWR
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  • A review of strategies and challenges of super critical water-cooled reactor (SCWR) deployment and technology readiness assessment of a SCWR- SMR design
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  • Applications of artificial intelligence (AI) technologies for supercritical water reactor (SCWR) and thermal hydraulic modeling of SCWR using deep learning
  • Physics-informed neural networks for supercritical pressure fluid convective heat transfer
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  • Prediction of heat transfer deterioration and recovery
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  • Design of active disturbance rejection control (ADRC) based control strategy for supercritical CO2 Brayton cycle-cooled reactor system
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  • Assessment of the failure time of the ECC-SMART supercritical reactor vessel in the late phase of a severe accident
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  • Generic results of the SCW-SMR pre-licensing study in the frame of ECC-SMART project
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  • LSTM networks for component damage predictions
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  • Progress on a pre-conceptual supercritical water-cooled small modular reactor – a deterministic safety assessment
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  • Assessment of corrosion behavior of cladding materials for SCW-SMR in static conditions : results obtained in ECC SMART project
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  • Modelling the long-term corrosion behaviour of candidate fuel cladding alloys for a supercritical water-cooled reactor
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  • Corrosion behaviour of alloy 800H and stainless steel 310S under conditions relevant to supercritical-water small modular reactor concepts
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  • In-situ electrochemical corrosion testing of 310S steel in supercritical water
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  • Long-term corrosion behavior and stress corrosion sensitivity of tubular cladding materials for supercritical water-cooled reactors
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  • In-situ corrosion study of 800H alloy in supercritical water
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  • Introduction of benchmark specifications for supercritical water loop
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  • Analyses of IBSCTH tests using system and CFD codes
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  • Loss of coolant flow accident analysis of chinese small modular supercritical water-cooled reactor
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  • Thermal-hydraulic design of printed circuit heat exchanger based on decoupled porous medium model
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  • Numerical simulation of a supercritical flow in a microchannel using the lattice boltzmann method
    Obtenir le chapitre
  • Experimental study on heat transfer characteristics of subcritical CO2/N2 mixtures in a vertical circulation loop
    Obtenir le chapitre
  • Numerical study of the intergranular stress corrosion cracking of nickelbased alloys in supercritical water
    Obtenir le chapitre
  • A comparative study of stress corrosion cracking initiation behavior of alumina-forming austenitic steels and base steels in supercritical water at 600 °C.
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  • Monte Carlo simulations of fast neutron radiolysis in supercritical water at temperatures of 400–600 °C and 25 MPa.
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  • Study of the effect of neutron irradiation on the corrosion and mechanical behaviour of candidate materials for SCW-SMR
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  • Irradiation effect on the corrosion behavior of sic in advanced reactors
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  • Evaluation of long-term exposure of 310s and 800h under conditions of SCW-SMR
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  • Experimental evaluation of fluid-to-fluid scaling models for deteriorated heat transfer at supercritical pressures
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  • Non-modal stability analysis of a lumped model of the super-critical water reactor
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  • Effect of deteriorated heat transfer on the onset of supercritical flow instability in heated channels
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  • Assessment of fluid-to-fluid similarity criteria to evaluate deterioration of heat transfer coefficients in flows of supercritical fluids
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  • Assessment of look-up tables for the prediction of heat transfer coefficient distribution in rod bundles cooled by supercritical water
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  • Experimental study on critical flow of supercritical carbon dioxide at transient state
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  • Breakaway oxidation of afa steel in supercritical carbon dioxide
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  • Revealing the superior oxidation resistance of alloy 690 in deaerated supercritical water and supercritical CO2 at 600 °C.
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  • Study of the corrosion behavior in supercritical water of an austenitic stainless steel 316L manufactured by Cold Spray
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  • Experimental study on supercritical water heat transfer in a 2x2 rod bundle
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  • Forced-convection heat transfer to scw with upward flow in short vertical bare tubes
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  • Heat transfer in short vertical 1- and 3-rod bundles cooled with supercritical water
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  • Analysis of heat transfer at supercritical conditions with machine learning algorithm
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  • Research on leakage and injection of high-energy fluids from pipelines and narrow gaps
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  • New developments of sub-channel CFD for rod bundles with wire wrapped spacers
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  • Modelling the influence of surface roughness on heat transfer at supercritical pressure
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  • Prediction of the heat transfer to supercritical pressure fluid at rough surface
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  • A study of the effect of pyramid roughness on turbulent heat transfer in supercritical water
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  • CFD modeling and validation of supercritical fluid heat transfer along rough wall surfaces
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  • Treatment and evaluation of surface roughness of fuel cladding for heat transfer experiments in supercritical fluids
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  • Analysis of roughness effects on turbulent heat transfer to supercritical water in a horizontal tube
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  • Discussing CFD analysis of horizontal and vertical upward flow under supercritical conditions
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  • Comparison of CFD analysis results of horizontal flow in SCW-SMR fuel assembly with and without wrapped wire spacers
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  • Fluid-to-fluid similarity and CFD predictions of heat transfer at supercritical pressure with influences of buoyancy and turbulence models : validation against IAEA benchmark
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  • Transient CFD analysis of supercritical CO2-based natural circulation LOOP
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  • Computational investigation of supercritical flow of water over eight rod bundle in a pressure tube
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  • Numerical prediction of heat transfer for supercritical fluids flowing horizontally and vertically downward using a new turbulence model
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  ISBN: 9791256081332

  Permalink: https://digital.casalini.it/5914364