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Water-Cooled Reactor Programs and Issues

Advances in Water Cooled Reactor Design and Technology
Monday, April 9, 3:05pm-5:10pm

  • Safety Design and evaluation of Loss of Forced Flow Accident of CRS1000
  • Comparative Studies of Sensitivity Analyses for Coupled VERA-CS/FRAPCON and VERA-CS/BISON Simulations
  • Evaluation of Degradation Effect of Fluoroelastomer in Simulated Severe Accident Environment of Nuclear Power Plants

Small Modular Reactors and Innovative Water-Cooled Reactors
Wednesday, April 11, 8:00am-10:00am

  • Production Learning in a Small Modular Reactor Supply Chain
  • The Impact of Modularization Strategies on Small Modular Reactor Construction Cost
  • Development of RBWR (Resource-Renewable BWR) for Recycling and Transmutation of Transuranium Elements (4) Radial Core Design Based on Radial Transport Effect
  • Preliminary design of hybrid small modular boiling water reactor with external superheater

High Temperature Reactors

High Temperature Reactors – 1
Monday, April 9, 1:05pm-2:45pm

  • Neutronics Modelling and Analysis of the TMSR-SF1 Core with Explicitly Described Fuel Pebble Loadings
  • A FEM study on the particle-wall impaction of graphite dusts in high temperature gas-cooled reactors (HTGR)
  • The Redistribution of Forces in a Pebble Bed Reactor due to Radiation Induced Pebble Shrinkage and Other Property Changes

High Temperature Reactors – 2
Wednesday, April 11, 10:20am-12:00pm

  • Feasibility study of the Pebble Bed High Temperature Test Facility
  • Cross flow and heat transfer characteristics of tube bundles with neighboring layers having opposite sense inclination
  • Model Validation for the Thermal Hydraulic Behavior in Molten Salt Natural Circulation

Advanced Reactors

Fast Neutron Reactors: ASTRID Research and Development — 1
Tuesday, April 10, 10:20am-12:00pm

  • ASTRID Project, General overview and status progress
  • ASTRID Nuclear Island design: update in French-Japanese joint team development of Decay Heat Removal systems
  • Progress in the design of the ASTRID nuclear island

Fast Neutron Reactors: ASTRID Research and Development — 2
Tuesday, April 10, 1:00pm-2:40pm

  • A New Experimental R&D Program Associated With The Corium Jet Impingement On The ASTRID Core Catcher Sacrificial Material
  • Seismic isolation system GEN IV
  • Steel Concrete modules in GEN IV

Fast Neutron Reactors: Analysis and Performance
Monday, April 9, 3:05pm-5:10pm

  • Multi-discipline Considered Design of Reactor Shutdown System for Prototype GEN-IV Sodium-cooled Fast Reactor
  • Analytical And Numerical Study Of The Stalling Phenomenon In An Electromagnetic Pump For A Sodium Fast Reactor
  • The GeN-transFoam Multiphysics solver’s application to the European Sodium Cooled Fast Reactor end of cycle simulation
  • Sodium Thermal-Hydraulic Test Program for Design Validation of Prototype Gen-IV Sodium-cooled Fast Reactor

Fast Neutron Reactors: Safety and Accident Analysis
Monday, April 9, 1:05pm-2:45pm

  • CFR-1000 UTOP Accident Analysis and Safety Assessment of Core Design During Concept Design Phase
  • New safety measures considered for European Sodium Fast Reactor in Horizon-2020 ESFR-SMART project
  • Means of Meeting Chapter 15 Requirements for a Small Modular Reactor Cooled by Lead-Bismuth
  • Preliminary Study on the Definition of Large Radioactive Release of Pool – type Sodium-cooled Fast Reactor

Molten Salt Reactors and Systems — 1
Tuesday, April 10, 8:00am-10:00am

  • Dynamics And Stability Analysis Of DFR Concept Using U-Pu And TRU Fuel Salts
  • Multiphysics study of the draining transients in the Molten Salt Fast Reactor
  • Nu-HOPE : The Experimental Platform for Heat Transfer Characteristics of Molten Salt
  • Preliminary design of Passive residual heat removal system for TMSR

Molten Salt Reactors and Systems — 2
Tuesday, April 10, 3:00pm-5:00pm

  • Investigation into Reactivity Feedback of FHR Designs with Alternative Coolants
  • Some Chemical Aspects of Molten-Salt Reactors Specifically in TRU Burning Applications
  • Corrosion and Redox Condition Control of Molten Li2BeF4 Salt for Molten Salt Reactors
  • Hybrid Fission – Fusion System for Sustainable Tritium Production

Advanced Reactors: Construction Innovation
Tuesday, April 10, 8:00am-10:00am

  • Extending modularization from modules to super modules: a cost evaluation of barge-transportable small modular reactors
  • Impact of Technological Innovation on Nuclear Power Plant Capital Costs
  • Advanced Manufacturing to Enable the Next Generation of Nuclear Plants
  • Seismic Evaluation for a Large-Sized Reactor Vessel targeting SFRs in Japan

Advanced Reactors: Economics Innovation
Wednesday, April 11, 8:00am-10:00am

  • Heat Storage for Variable Electricity Production from Base-Load Reactors with Sodium or Salt in the Secondary Loop
  • Exploring the Role of Advanced Nuclear in Future Energy Markets: Economic Drivers and Barriers in the United States
  • Comparison Of Net Present Value For Construction Projects Of Two Offshore Floating Nuclear Power Plant Designs, Using A Monte Carlo Method For Evaluation Of The Project Uncertainties
  • Westinghouse Lead Fast Reactor Development: Safety And Economics Can Coexist

Light Water Reactors: Advanced Concepts and Technologies
Wednesday, April 11, 10:20am-12:00pm

  • Preliminary Core and Fuel Design of BWR with Muti-Axial Fuel Shuffling
  • Discussion on Thermal-hydraulic Analysis for Low-pressure Reactor HAPPY200
  • Systematic Design Of Passive In-Core Cooling System Based On Hybrid Control Rod-Heat Pipe For Small Modular Reactor

Operation, Performance and Reliability Management

Operation, Performance and Reliability Management – 1
Monday, April 9, 3:05pm-5:10pm

  • Design Vulnerability of the Ground Fault Protection System for the Preferred Power Supply of Nuclear Power Plants
  • HuREX: An integrated analysis framework for operator reliability data and its supporting tool
  • Industrial Control System Testbed for Cybersecurity Research with Industrial Process Data
  • Human performance benefits gained by dynamic instructions compared to smart PDFs

Operation, Performance and Reliability Management – 2
Wednesday, April 11, 10:20am-12:00pm

  • Evaluation of Feedback Reactivity Coefficients by Inverse kinetics in Monju
  • Estimation Of The Radioactive Contamination Density From The Spatial Dose With Machine Learning

Plant Safety Assessment, Regulatory and Licensing Issues

Severe Accident Analysis
Monday, April 9, 3:05pm-5:10pm

  • Experimental Study of the Effect of Molybdenum on Iodine Transport in the Primary Circuit during a Severe Nuclear Power Plant Accident
  • Effect of hydrodynamics on retention of elemental iodine in a wet scrubber
  • Effects of FCVS Operating Strategies on the Cesium Releases during Severe Accidents
  • Progress In Understanding Fukushima Unit 1 Severe Accident Through Forensic MELCOR Analyses

Probabilistic Risk and Hazard Analyses
Tuesday, April 10, 8:00am-10:00am

  • Nuclear Power Plant Design Resilience against Hazard Combinations – A Multi-Discipline View
  • SFP PSA development for UK ABWR
  • Probabilistic Risk Assessment of the Spent Nuclear Fuel Loading Process in Light Water Reactor Systems
  • Hazard Assessment of the Molten Salt Reactor Experiment

Design, Licensing and Safety Insights
Tuesday, April 10, 3:00pm-5:00pm

  • 60 Years of Contributing to Reactor Safety: Insights on ACRS Power Reactor Licensing Reviews
  • The European Utility Requirements for advanced LWR – Issue of EUR revision E and ongoing assessments
  • Application Of Practical Elimination Methodology For Gen Iv Reactors
  • Literature Review On Knowledge Retention, Engineering Design Projects, And License Renewal In Support Of The Subsistence Of The U.S. Nuclear Power Industry

Safety and Accident Analysis
Tuesday, April 10, 3:00pm-5:00pm

  • Bowtie methodology in Nuclear Power Plant Safety
  • Evaluation of Loop Seal Clearance and Reformation during SBLOCA of APR1400
  • Simulation of Steam Generator Tube Rupture Accident in a Pressurized Water Reactor
  • Experimental and Numerical Investigations on Hydraulics of Prototypical Porous Concretes for an Ex-vessel Bottom Cooling Concept

Advanced Safety Models & Issues
Wednesday, April 11, 8:00am-10:00am

  • The UK Nuclear R&D Program on Digital Nuclear Reactor Design – Modelling, Simulation, and Virtual Engineering
  • ASTRID – Practical Elimination Of “Brutal Failure Of Supporting Core Structures”
  • Development of Molten Corium and Zirconia Refractory Material Interaction Model
  • Modeling of Coordinated Cyber and Physical Attacks at Nuclear Power Plants

Reactor Physics and Analysis

Reactor Physics and Analysis – 1
Monday, April 9, 1:05pm-2:45pm

  • CATHARE3 transient analysis of an innovative Power Conversion System based on the Brayton cycle modelled with real gas Equations Of State
  • Advanced Fuels Cost Performance Assessment for the Westinghouse LFR
  • Development of a TRACE/PARCS Core Model for APR1400 MSLB Accident Analysis

Reactor Physics and Analysis – 2
Tuesday, April 10, 1:00pm-2:40pm

  • A semi-analytical Matrix to extract keff and/or critical parameters of fissile Cores- as an Aid for deterministic Calculations of Multi-Group Neutronics
  • Developing and Verification of the New Resonance Self-shielding Module in the Lattice Physics Code cosLATC
  • Depletion and Lifetime Performance Analysis of Advanced Manufactured Control Elements in the High Flux Isotope Reactor (HFIR)

Reactor Physics and Analysis of Fast Reactors
Wednesday, April 11, 10:20am-12:00pm

  • Investigation of the Core Neutronics Analysis Conditions for Evaluation of Burn-up Nuclear Characteristics of Next-Generation Fast Reactors
  • Comparative Study on Prediction Accuracy Improvement Methods with the Use of Integral Experiments for Neutronic Characteristics of Fast Reactors
  • Improvement of Sodium Fast Reactor Control Rods Calculations with APOLLO3®

Thermal Hydraulics Analysis and Testing

CHF Modeling and Analysis
Monday, April 9, 1:05pm-2:45pm

  • Mechanistic Modeling of Departure from Nucleate Boiling under Transient Scenarios
  • Safety Margin Characterization for ATR high power fueled experiments
  • The latest review of CHF enhancement methods in nuclear systems

Heat Exchanger Testing, Modeling and Analysis
Tuesday, April 10, 3:00pm-5:00pm

  • Design of a compact heat exchanger and heat transfer investigations of a scaled down sCO2-HeRo-system
  • Experimental Methods to Model and Validate Coiled Tube Gas Heater for Nuclear Brayton Cycles
  • Numerical Investigation of Thermal Boundary Conditions of a High-Temperature PCHE with Zigzag Flow Channels
  • Experimental study on condensation heat transfer for air-cooled shell and tube heat exchanger in long term passive cooling system

Severe Accident Testing, Modeling and Analysis –I
Monday, April 9, 3:05pm-5:10pm

  • Influence of Steam Production on Particulate Debris Bed Spreading
  • Development of Passive Debris Cooling System
  • Application of Several Numerical Methods for Ex-Vessel Debris Bed Formation in a LWR Severe Accident
  • A method for predicting the configuration of corium pool in RPV lower plenum

Severe Accident Testing, Modeling and Analysis — II
Tuesday, April 10, 10:20am-12:00pm

  • Aerosol depletion in natural circulation in simplified geometry
  • Numerical Research on Melting Behavior of Shroud and Basket of ACP1000 during a Severe Accident
  • MAAP5 Simulation Of PWR High-Pressure Core Melting Severe Accident Due To Small-Break LOCA

Thermal Hydraulics Experiment, Testing, and Analysis
Tuesday, April 10, 8:00am-10:00am

  • Investigation Of Interfacial Waves Behavior During Quenching Of A Vertical Cylinder Using An Image Processing Technique
  • Design of close and open channels experiments to study molten salt flows
  • Analysis of initially subcooled leakage flows in a narrow through-wall crack at low Reynolds-numbers
  • Study of CCFL Two-Phase Flow at Upper Tie Plate of Fuel Bundle to Evaluate Spray Cooling Capability in Spent Fuel Pool

Code Development, Validation and Application — I
Tuesday, April 10, 3:00pm-5:00pm

  • Contribution of the OECD PKL-3 Project to the Validation of the System Code ATHLET
  • Accident Tolerant Fuels Benchmark Calculation by MELCOR and TRACE for a Simplified Generic Pressure Water Reactor
  • Thermal Hydraulic Performance of the Decay Heat Removal System for the Integral Inherently Safe Light Water Reactor
  • Implementation of Grid Spacer and Mixing Vane Model for Subchannel Scale Thermal-Hydraulic Analysis using CUPID

Code Development, Validation and Application — II
Wednesday, April 11, 8:00am-10:00am

  • Numerical simulations at different scales for the CIRCE facility
  • System Thermal Hydraulics and Multiscale Simulations of the Dissymmetric Transient in the Phénix Reactor
  • Pronghorn: A Porous Media Thermal-Hydraulics Core Simulator and its Validation with the SANA Experiments
  • Phase Change Simulation of the Plasma Facing Material in Fusion Demo Reactor with Mesh Adaptation Technique

General Thermal Hydraulics
Tuesday, April 10, 10:20am-12:00pm

  • Thermal Hydraulics Analysis of High Temperature Gas-cooled Nuclear Reactor Using Multiphysics Software
  • On the use of inverse problem methods in nuclear reactors design applications
  • Study on the relationship between flow maldistribution and heat transfer performance of air-cooled heat exchangers with different entrances and exits

Computational Fluid Dynamics Modeling and Analysis — I
Monday, April 9, 3:05pm-5:10pm

  • Simulation of Two-Phase Flows with Condensation in CFD Applications
  • Multi-bubble Flow Boiling Simulation Using Interface Tracking Method
  • Simulating Sodium Pool Natural Circulation In RVACS Operation Using CFD
  • Sub-channel Void Fraction Distribution in a 5X5 mock-up of PWR fuel assembly under sub-cooled flow boiling

Computational Fluid Dynamics Modeling and Analysis — II
Tuesday, April 10, 8:00am-10:00am

  • Experimental and Numerical Investigation of Flow Phenomena in a Vertical T-junction Configuration
  • Bubble Dynamics Analysis in PWR Two-Phase Flow Simulations using Interface Tracking Methods
  • Assessment of a Robust Second Generation URANS Turbulence Model for Prediction of Thermal Striping in T-junction Configurations
  • Reducing BWR Jet Pump Vibration of Slip Joints by full scale experiments and theoretical studies

Computational Fluid Dynamics Modeling and Analysis — III
Tuesday, April 10, 1:00pm-2:40pm

  • High fidelity simulations for characterizing Sauter mean diameter of droplets in the DFFB regime
  • Thermal Stratification Analysis for Sodium Fast Reactors
  • A Numerical Study for Applicability of Water Tests to the Sodium Pool Natural Circulation Analysis

Computational Fluid Dynamics Modeling and Analysis — IV
Wednesday, April 11, 10:20am-12:00pm

  • Transient CFD Analysis of the Thermal Mixing of the Feedwater in the Downcomer of a BWR
  • Coarse-Grid Computational Fluid Dynamics (CG-CFD) Error Prediction via Random Forest Regression

Fuel Cycle and Waste Management

Nuclear Fuel Cycle Analysis
Monday, April 9, 1:05pm-2:45pm

  • French scenarios toward fast plutonium multi-recycling in PWR
  • Scenario toward a mixed fleet of breeder SFR and EPR to balance the plutonium inventory in France
  • Fuel Cycle and Safety Margin Analyses for MIT Reactor Low Enriched Uranium Transition Core Development

Advanced Transmutation Systems and Modeling
 Wednesday, April 11, 8:00am-10:00am

  • The Belgian MYRRHA ADS Programme. Part 1: The new phased implementation plan
  • The Belgian MYRRHA ADS Programme. Part 2: Recent developments in the reactor primary system
  • MUFFSgenMC: An Open Source MUon Flexible Framework for Spectral GENeration for Monte Carlo Applications

Spent Fuel and Structural Monitoring
Tuesday, April 10, 1:00pm-2:40pm

  • Muon-Computed Tomography By Tracing Cosmic Ray Muon Trajectories For Imaging Spent Nuclear Fuel In Dry Storage Casks
  • Health monitoring on medium scale structures using acoustic emission methods
  • Sensor Requirements for Detection and Characterization of Stress Corrosion Cracking in Welded Stainless-Steel Canisters

Waste Management
Tuesday, April 10, 10:20am-12:00pm

  • Salt Cleanup and Waste Solidification into Iron Phosphate or Borosilicate Glass with Halide Recycle for Fission and Fusion Salt Reactors
  • Low Temperature Facile Sintering of Silicon-Substituted Calcium Hydroxyapatite for the Immobilization of Radioactive Waste
  • Multiscale modeling of an advanced ceramic waste form using MOOSE

Materials and Structural Issues

Structural Issues and Advanced Processes
Monday, April 9, 1:05pm-2:45pm

  • Load Carrying Capacity Of Thrust Bearing For Nuclear Coolant Pump With Boundary Slippage And Elastic Deformation
  • Considerations from the Benchmark Comparison of OXBOW against IWGFR Mechanical Analysis Codes
  • High-cycle Acoustic Loads Structural Evaluation of BWR Steam Dryer Modification
  • Advanced Welding Technology Development for Nuclear Reactor Repair

Environmental Compatibility at High Temperature — 1
Wednesday, April 11, 8:00am-10:00am

  • Thermophysical Properties of Stainless Steel Containing 5mass%-B4C in the Solid Phase
  • Thermophysical Properties of Molten Stainless-Steel Containing 5mass%-B4C
  • Serrated Flow in Alloy 709
  • Critical Review On Molten Salt Corrosion For Nuclear Applications

Environmental Compatibility at High Temperature — 2
Wednesday, April 11, 10:20am-12:00pm

  • Graphite in salt-cooled high temperature reactors: Known issues from past experience and proposed path forward for their mitigation
  • Experiment on the Compatibility of Single and Bimetallic Alloys in a Subscale Flowing FLiBe Loop

Accident Tolerant Fuel Research and Development — 1
Tuesday, April 10, 10:20am-12:00pm

  • High temperature interaction of SiC and Zry-4
  • Quenching test of SiC-SiC composite cladding
  • Analysis Of Thermal Creep For Uranium Silicide Fuel Using Bison

Tolerant Fuel Research and Development — 2
Tuesday, April 10, 1:00pm-2:40pm

  • Modelling RIA Experiments By FRAPCON With Advanced Cladding Materials
  • Improvement of the high-temperature oxidation resistance of Zr alloy cladding by surface modification with aluminum-containing ternary carbide coatings

Nuclear Energy and Global Environment

Innovative Hybrid Nuclear Energy Systems
Tuesday, April 10, 8:00am-10:00am

  • Design and Operation of an Electric Peaking/Industrial Steam Production Unit for SMRs
  • Absorption Chiller and Stratified Chilled-Water Storage Tank Configurations for Coupling to a Small Modular Reactor
  • Supercritical Carbon Dioxide Brayton cycle for hybridization of a small modular reactor and a concentrated solar power plant with thermal energy storage
  • Predictive Modeling Of A Paradigm Mechanical Cooling Tower

Nuclear Energy and Global Environment
Tuesday, April 10, 3:00pm-5:00pm

  • Greenhouse Gas Assessment for the Canadian Nuclear Fuel Life Cycle
  • The Global Energy Challenges Of The 21st Century: Role Of Nuclear Energy
  • Energy and Nuclear Power Planning Study for Bangladesh Using WASP-IV
  • MIT-Japan Study: Future of Nuclear Power in a Low-Carbon World: The Need for Dispatchable Energy