Technical Meeting on State-of-the-art Thermal Hydraulics of Fast Reactors

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Sessions*

Wrap Up Day 3

Wrap Up Day 2

Track I: Fundamental thermal hydraulics

Closing Session

Track II: Test Facilities and Experimental Thermal Hydraulics (2.1)

Track II: Test Facilities and Experimental Thermal Hydraulics (2.2)

Track III: Computational Modelling & Simulation (3.1)

Track III: Computational Modelling & Simulation (3.2)

Track IV: Thermal Hydraulics of Transients and Accidents (4.1)

Track IV: Thermal Hydraulics of Transients and Accidents (4.2)

Track V: Multiscale and Multiphysics Modelling (5.2)

Wrap Up Day 1

Track V: Multiscale and Multiphysics Modelling (5.1)

Panel 2: How to use Modern thermal hydraulics Tools and Methods in Licensing Application

Panel 1: Legacy reactor data for validation of fast reactor thermal hydraulics & Availability and need of experimental data for validation and verification

Social Event - Invited Dinner by ENEA

IAEA Fast Reactors Activities

General Discussion

ENEA Technical Tour

Track VI: Verification, Validation and Uncertainty Analysis

Opening Session

Poster Session

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Contributions*

A study of thermophysical and physicochemical characteristics of the KALLA experimental facility (in session "Track III: Computational Modelling & Simulation (3.1)")

Applicability Enhancement of the SAS4A/SASSYS-1 Computer Code to Lead Fast Reactor Systems (in session "Track VI: Verification, Validation and Uncertainty Analysis")

Design Optimization of flow Distribution Device in Bottom Header of IHX of Future FBRs (in session "Poster Session")

Development of ARKADIA-Design for Design Optimization Support - Application of coupling method using multi-level simulation technique for plant thermal-hydraulics analysis - (in session "Poster Session")

Development of ARKADIA-Safety for Severe Accident Evaluation of Sodium-cooled Fast Reactors (in session "Poster Session")

Development of Efficient Improved Core Thermal-Hydraulics Predictive Capability for Fast Reactors (in session "Track V: Multiscale and Multiphysics Modelling (5.2)")

Development of one dimensional PINET code and analysis of heat removal in oscillating sodium column (in session "Poster Session")

Development of Plant Lifecycle Optimization Method, ARKADIA for Advanced Reactors (in session "Track V: Multiscale and Multiphysics Modelling (5.2)")

Estimation of FPs Release from Sodium Pool under BDBA conditions in a Sodium Fast Reactor (in session "Track V: Multiscale and Multiphysics Modelling (5.1)")

EXPERIMENTAL AND CALCULATION INVESTIGATIONS OF HYDRODYNAMICS AND HEAT EXCHANGE IN LIQUID METAL TURBULENT FLOWS IN FAST REACTOR FUEL ASSEMBLIES (in session "Track I: Fundamental thermal hydraulics")

Experimental thermal hydraulics studies in large scale model test facilities towards development and validation of FBR components (in session "Track II: Test Facilities and Experimental Thermal Hydraulics (2.1)")

Experimental thermal-hydraulic R&D achievements and needs for MYRRHA (in session "Track II: Test Facilities and Experimental Thermal Hydraulics (2.1)")

Extension of the DYN3D/ATHLET code system to transient analyses of SFRs (in session "Poster Session")

Fast reactor multi-scale and multi-physics modelling at NRG (in session "Track V: Multiscale and Multiphysics Modelling (5.1)")

Fast Reactor Thermal Hydraulics in the Dutch PIONEER program (in session "Track III: Computational Modelling & Simulation (3.1)")

FLOW BLOCKAGE THERMAL-HYDRAULIC ASSESSMENT IN ALFRED FUEL ASSEMBLY (in session "Track IV: Thermal Hydraulics of Transients and Accidents (4.1)")

Forced to natural circulation transients in wire-spaced fuel pin bundle (in session "Track I: Fundamental thermal hydraulics")

FUNDAMENTAL AND APPLIED INVESTIGATONS OF THE LIQUID-METAL COOLED FAST REACTOR THERMAL HYDRAULICS (ACHIEVED RESULTS AND FURTHER INVESTIGATION ISSUES) (in session "Track II: Test Facilities and Experimental Thermal Hydraulics (2.1)")

Heat transfer studies with steam generator and decay heat removal system for FBRs (in session "Poster Session")

Implementing of an Isolated Condenser with non-condensable gases passive safety system originated in the ALFRED LFR demonstrator plant - to a CANDU 6 plant that was a general active safety systems designed plant. (in session "Poster Session")

Improvement of ALFRED thermal hydraulics through experiments and numerical studies (in session "Track II: Test Facilities and Experimental Thermal Hydraulics (2.1)")

MODELLING OF THE DYNASTY EXPERIMENTAL FACILITY FOR NATURAL CIRCULATION UNDER DISTRIBUTED HEATING (in session "Track III: Computational Modelling & Simulation (3.2)")

NINE THERMAL HYDRAULIC CONTRIBUTION IN IAEA CRPS FOCUSED ON SODIUM FAST REACTORS (in session "Track VI: Verification, Validation and Uncertainty Analysis")

Numerical analyses of the CIRCE-THETIS facility by mean of STH and CFD codes (in session "Poster Session")

Preliminary Assessment of the Safety Performance of Westinghouse LFR (in session "Track IV: Thermal Hydraulics of Transients and Accidents (4.1)")

REDUCED ORDER MODEL FOR THERMOHYDRAULICS PROBLEMS: TOWARDS UNCERTAINTY QUANTIFICATION FOR CFD SIMULATIONS (in session "Track VI: Verification, Validation and Uncertainty Analysis")

Review and future perspectives of the coupled STH/CFD applications performed at the University of Pisa (in session "Track V: Multiscale and Multiphysics Modelling (5.1)")

Review and main outcomes from the experimental program carried on the PLATEAU facility. (in session "Track II: Test Facilities and Experimental Thermal Hydraulics (2.2)")

Road to qualification of the ANEO+ sub-channel code (in session "Poster Session")

Safety Review and Assessment of Core Thermal Hydraulics of PFBR (in session "Track III: Computational Modelling & Simulation (3.2)")

SIMMER Modeling of Accident Initiation Phase in Sodium Fast Reactors (in session "Track IV: Thermal Hydraulics of Transients and Accidents (4.2)")

Spatio-temporal evolution of sodium combustion aerosol and thermal distribution during sodium pool fire in a confined environment (in session "Track II: Test Facilities and Experimental Thermal Hydraulics (2.2)")

STANDARD CFD TECHNIQUE FOR SODIUM TO SODIUM HEAT EXCHANGERs (in session "Poster Session")

State-of-the-art review of the T/H system codes RELAP5 for HLM applications. (in session "Track III: Computational Modelling & Simulation (3.1)")

State-of-the-art turbulent heat flux modelling for low-Prandtl flows (in session "Track I: Fundamental thermal hydraulics")

Studies of liquid metal boiling in fuel assemblies of fast reactors in accident conditions (in session "Track IV: Thermal Hydraulics of Transients and Accidents (4.2)")

Subchannel modelling capabilities of RELAP5-3D© for wire-spaced fuel pin bundle (in session "Track III: Computational Modelling & Simulation (3.2)")

Test Matrices definition for the SIRIO facility in the frame of the H2020-PIACE project: pre-test simulation results and conclusions (in session "Track II: Test Facilities and Experimental Thermal Hydraulics (2.2)")

THE LIFUS5 SEPARATE EFFECT TEST FACILITY EXPERIMENTAL PROGRAMME (in session "Track II: Test Facilities and Experimental Thermal Hydraulics (2.2)")

THERMAL HYDRAULICS STUDIES FOR FUTURE INDIAN FAST BREEDER REACTORS (in session "Poster Session")

Thermal-hydraulic analysis of HLM cooled fuel pin bundle (in session "Poster Session")

Thermo-fluid dynamic analysis of HLM pool. CIRCE Experiments (in session "Track IV: Thermal Hydraulics of Transients and Accidents (4.1)")

TIFONE: a design-oriented code for the inter-wrapper flow and heat transfer in liquid metal-cooled reactors (in session "Track III: Computational Modelling & Simulation (3.2)")

VALIDATION OF RANS SIMULATIONS ON A 61-PIN WIRE-WRAPPED FAST-REACTOR FUEL ASSEMBLY UNDER THE PRESENCE OF LOCALIZED BLOCKAGES (in session "Track VI: Verification, Validation and Uncertainty Analysis")

Validation Study of Sodium Pool Fire Modeling Efforts in MELCOR and SPHINCS Codes (in session "Track IV: Thermal Hydraulics of Transients and Accidents (4.2)")

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Events scheduled on*

9/26/22

9/27/22

9/28/22

9/29/22

9/30/22

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