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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