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RERTR-2021 International Meeting

RERTR-2021 International Meeting on Reduced Enrichment for Research and Test Reactors

RERTR-2021 International Meeting on Reduced Enrichment for Research and Test Reactors

RERTR-2021 International Meeting on Reduced Enrichment for Research and Test Reactors

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Welcome to the RERTR International Meeting

Post author By egsadmin
Post date February 17, 2021
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Poster Sessions

4.01 Update on the Industrialization Phase of the KUCA Dry Cores Conversion Project
4.02 First Steps Towards Validation of Power Distribution Calculations for Involute Plate Reactors
4.03 Involute Working Group – Validation of CFD Turbulence Models for Steady-State Safety Analysis
4.04 MITR End Fitting Structural Rigidity Analysis
4.05 Evaluation of Multiple Techniques for Rapid Analysis of Uranium Isotopes
4.06 Startup Test Plan and Predictions for Low-Enriched Uranium Fuel Conversion at the University of Missouri Research Reactor
4.07 Measurement of the emissivity of U-Mo at different tarnish colours and temperatures
4.08 UMo Atomization – Numerical Simulation with SPH Method
4.09 From the Conventional to an Innovative Manufacturing Process of U3Si2/Al Fuel Plates
4.10 Startup Plan for Initial LEU Fueled Core of MIT Reactor
4.11 Enhancing Isotope Mixing During U-10Mo Downblend Casting with Electromagnetic Stirring
4.12 Decommissioning of IIN-3M Pulse Research Reactor of JSC “FOTON” in Tashkent
4.13 Additive Manufacturing of Nuclear Component
4.14 Regression Testing for BR2 RELAP5 Models
4.15 Developments of U-Mo Monolithic Plates with Gradient Foils
4.16 Thermal Conductivity Measurement of the Al-UMo Interaction Layer Induced by Heavy Ion Irradiation
4.17 Development, Testing, and Usage of the ADDER Software for Fuel Management and Depletion Analysis
4.18 The Final Stretch: Tackling Remaining HEU Minimization Challenges
4.19 UMo Atomization – New Pilot Equipment Implemented in CERCA
4.20 The TUM Nuclear Fuel Laboratory: Current Developments and Planned Expansion
4.21 Low Enrichment Uranium Nuclear Fuel Based on Uranium-Zirconium Carbonitride: Performance of Methodical Reactor Experiment and the Results Thereof
4.22 Laser Shock Interface Strength Characterization of MP-1 Fresh Fuel Plates
4.23 Discrete-Continuous Modelling for Improved Core Parameter Calculations
4.24 Y-12 National Security Complex LEU-Mo Feedstock Fabrication Update
4.25 Multi-physics Feedback on MTR Research Reactors Core Design
4.26 Activities in Upgrading the NBSR Model
4.27 Validation of System Transient Codes RELAP5 and TRACE
4.28 Preliminary Structural Analysis of NBSR LEU-10Mo Fuel Plate
4.29 Effect of Microstructure and Rolling Treatment on Static Recrystallization Behavior in U-10Mo Using a Microstructure-Based Modeling and Machine Learning Algorithm
4.30 Verification and Validation of COMSOL Multiphysics to Support HFIR Applications

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