Annual Meeting 2020 / Volume 122

Table of Contents

Author Index

Full Issue

Opening Plenary

Kevin O'Kula

President's Special Session

Marilyn Kray (Exelon)

Improving Long-Term Economic Competitiveness: Status of Nuclear Hydrogen Production Projects

Kevin O'Kula

ANS Position Statement on the Use of Low Eneriched Uranium in Space–Panel

Jeffrey King (CSM)

Nuclear Energy’s Role in Climate Change Policy–Panel

Leah Parks (NRC)

Workforce Development–Panel

James Byrne (Byrne & Associates)

Uranium Mine Reclamation–Panel

James Byrne (Byrne & Associates)

Mercury Remediation Process Optimization for Clayey Soil

Michael Smith (UNC), Sven Bader (Orano), Thomas Koch (UNC), Arthur Niemoller (Orano)

Hydrogen Economy in Champaign-Urbana, IL

Roberto E. Fairhurst Agosta, Samuel G. Dotson, Kathryn D. Huff (UIUC)

Material Requirements for a Green New Deal

Barry L. Butterfield (Individual), Daniel B. Bullen (DNFSB)

Nuclear Science Training for Secondary School Teachers at Argonne National Laboratory - 2019

David Grabaskas, Sunaree Hamilton (ANL), Gerald Reyes (IAEA), Micah Pacheco (Dept. of Education, Philippines), Habibah Adnan (Malaysian Nuclear Agency), John Domyancich, DeeDee Rudisel, Natalie Zender (ANL)

Digital Assistant Tool for Long Term Operation of Aging Assets

Micah Tinklepaugh, Emma Wong (EPRI)

Innovative Way to Save Tens of Millions of Dollars and Improve Plant Performance

Gary R. Cavanaugh, Bruce W. O’Brien (Marathon Consulting Group)

PLuS Alliance Nuclear Engineering Online Course Exchange Program

Keith E. Holbert (Arizona State Univ.), John Fletcher, Patrick A. Burr, Edward G. Obbard (Univ. New South Wales)

Flawless Fusion in Less Than 60 Seconds Over Similar or Dissimilar Material

Paul Cheng (Univ. Alberta)

Considerations for Bringing New Suppliers into the Nuclear Supply Chain

Elina Teplinsky, Anne Leidich (Pillsbury Winthrop Shaw Pittman)

Focus on Communications—I–Panel

Mimi Limbach (Potomac Communications)

Focus on Communications—II–Panel

Mimi Limbach (Potomac Communications)

Waste Management and Fuel Cycle Innovation Challenges for Advanced Nuclear Reactors - Gen IV (Including International Perspectives)–Panel

Steve Napier (UK NNL)

Analysis of Potential Standardized Canister Deployments at Commercial US Nuclear Reactor Sites

Robby Joseph, Riley Cumberland, Rob Howard (ORNL)

Rapid Analytic Determination of Dry Cask Storage Canister Internal Temperatures

Evan T. Palmer, Iza G. Lantgios, Matthew M. Barry (Univ. of Pittsburgh)

Development of a CFD Model for the Drying of Aluminum-clad Spent Fuel

Nathaniel Cooper (Univ. of South Carolina), Tanvir Farouk, Jamil Khan, Yi Wang, Rebecca Smith (INL), Travis Knight (Univ. of South Carolina)

Inverse Depletion of Used Nuclear Fuel: a Bayesian Approach

Bassam A. Khuwaileh, Fatima I. Al-Hamadi, Mohammad A. Al-Shabi, Walid A. Metwally (Univ. of Sharjah)

Fuel Storage and Transportation for the Next Generation of Reactors–Panel

Sven Bader (Orano)

Waste Disposal Solutions in a Country with No HLW Repository–Panel

Sven Bader (Orano)

Examples of Technology Applicable to In-Situ Waste Characterization

J. F. Lucchini, D. M. Brigham, B. A. Crawford (LANL)

Digestion of Zircaloy Cladding for UNF using Sulfur Chloride Reagents

Craig Barnes, Breanna Vestal (Univ. of Tenn., Knoxville), Guillermo (Bill) Daniel DelCul (ORNL)

Photodecomposition of Organoiodides to Molecular Iodine as Pretreatment for Adsorption

John Stanford, Tejaswini Vaidya, Vivek Utgikar, Krishnan Raja (Univ. of Idaho), Piyush Sabharwall (INL)

Fenton-Like Process for Treatment of IRN-150 Resin with Simulated 14C

Junsung Jeon, M. Aamir Hafeez, Wooyong Um (Pohang Univ. of Science and Technology)

Removal of Sr2+ in Aqueous Solution Using MOF-1@MnO2 Composites

Sang-June Choi, Jung-Weon Choi (Kyungpook Nat'l Univ.)

DANESS v9: Dynamic Analysis of Advanced Nuclear Energy Systems

Luc Van Den Durpel (Nuclear-21)

SNF Consumption and Disposal using the Mu*STAR Molten-Salt Accelerator-Driven Subcritical Reactor

Robert J. Abrams, Mary Anne Cummings, Rolland P. Johnson, J. D. Lobo, Thomas J. Roberts (Muons, Inc.)

Temperature Sensor Technology Gaps for Nuclear Environments

Dan Floyd (Univ. of Tenn., Knoxville), N. Dianne Bull Ezell (ORNL), Richard T. Wood (Univ. of Tenn., Knoxville)

A Wireless Resonance Inductive-Capacitive Sensor System for Nuclear Reactor

Yuan Gao, Jerry Potts, Heng Ban (Univ. of Pittsburgh), Daniel Wachs (INL)

Electromagnetic Coupling for Wireless Signal Transmission in Nuclear Reactors

Jerry Potts, Yuan Gao, Heng Ban (Univ. of Pittsburgh), Daniel Wachs (INL)

Embedding Sensors in Metal and Ceramic Structures

Christian M. Petrie (ORNL)

The Nuclear Digital I&C System Supply Chain Cyber-Attack Surface

Shannon L. Eggers (INL)

Development of a Framework for NPP Process-Aware Cyber Attack Detection and Diagnosis Methodology

Chanyoung Lee, Poong Hyun Seong (KAIST)

Advantages of a Game-Theoretic Approach for Nuclear Cybersecurity

Lee T. Maccarone, Daniel G. Cole (Univ. of Pittsburgh)

Nuclear Instrumentation and Control Simulation (NICSim) Platform for Investigating Cybersecurity Risks

Mohamed S. El-Genk, Timothy M. Schriener (Univ. of New Mexico)

Programmable Logic Controller of a Pressurized Water Reactor Core Protection Calculator

Andrew Hahn, Mohamed S. El-Genk, Timothy M. Schriener (Univ. of New Mexico)

Pressurizer Model and PLCs for Investigation of Cybersecurity of PWR Plants

Ragai M. Altamimi, Mohamed S. El-Genk, Timothy M. Schriener (Univ. of New Mexico)

Steam Generator Model and Controller for Cybersecurity Analyses of Digital I&C Systems in PWR Plants

Timothy M. Schriener, Mohamed S. El-Genk (Univ. of New Mexico)

Control and Load Balancing with an IPWR Module to Support Deep Renewables Penetration

Richard Bisson, Jamie Coble (Univ. of Tenn., Knoxville)

Load Following Characteristics of Multi-Modular Reactors

Areai Nuerlan, Rizwan-uddin (Univ. of Ill., Urbana-Champaign), Fuyu Zhao (Xi’an Jiaotong Univ.)

Using Auxiliary Particle Filter to Estimate Remaining Useful Life

Hang Xiao, Jamie B. Coble, J. Wesley Hines (Univ. of Tenn.)

Progress Toward Molten Salt Reactor Heat Exchanger On-Line Monitoring

S. W. Glass, M.S. Good, E.L. Forsi, R. O. Montgomery (PNNL)

Automated Functional Testing for Nuclear Digital Instrumentation and Control Systems

Greg Morton, Brent Shumaker, Dan McCarter, Chris Maddux (AMS)

Study on the Test Approach and Development Method of APR1400 Training Simulator with Virtual DCS

Sung Kon Kang, Kyung Min Kim, Min Seok Kim (Korea Hydro Nuclear Power Co.)

Development of an NPP VDCS Verification Platform

XY Wei, JY Qing, PW Sun, Q Ma, HW Sun (Xi’an Jiaotong Univ.)

Betavoltaic Nuclear Microbattery Based on Graphene/Si Schottky Junction

Xiaoyu Wang (Univ. of Science and Technology of China), Weiping Liu (Chinese Academy of Sciences), Jiachen Zhang (Univ. of Science and Technology of China), Yuncheng Han, Taosheng Li, Chunjing Li (Chinese Academy of Sciences)

Correlation of Absolute 238U Bioavailability (238U-ABA) and 238U Bioaccessibility Fraction (238U-BAF) Using IAEA-312 Standard Reference Soil

Nur Shahidah Abdul Rashid (Pohang Univ. of Science and Technology), Nur Syamimi Diyana Rodzi, Khoo Kok Siong (The Nat'l Univ. of Malaysia), Wooyong Um (Pohang Univ. of Science and Technology)

Neutronics Analysis for Designing a Low Activation Heated Test Cell

Michael Buratynski, William J. Walters (Penn State Univ.)

Predicting Background Count Rate of a Mobile Detector using an Optimal Linear Ensemble of Learning Kernel Machines

Miltiadis Alamaniotis (Univ. of Texas, San Antonio)

Impact of Fission Product Content on Phase Development in U3Si2 Fuel

Kaitlin E. Johnson (Univ. of South Carolina), Denise L. Adorno (Westinghouse Electric Sweden), Vancho Kocevski, Tashiema L. Ulrich, Joshua T. White (LANL), Antoine Claisse (Westinghouse Electric Sweden), Jacob W. McMurray (ORNL), Theodore M. Besmann (Univ. of South Carolina)

An Alternative Synthesis Route to U3Si2

Adrian Gonzales, Elizabeth Sooby Wood (Univ. of Texas, San Antonio,), Kent Coulter (Southwest Research Institute)

Failure Behavior of Nuclear-grade FeCrAl Cladding under Simulated Pellet-cladding Mechanical Interaction Conditions

B. Garrison, R. R. Lowden (ORNL), M. N. Cinbiz (ORNL/INL), N. R. Brown (Univ. of Tenn., Knoxville), K. Linton (ORNL)

Accident Tolerance of Zircaloy-2 and FeCrAl Under Simulated Cyclic Dryout Conditions

Ken Kane (ORNL), Soon Lee (Univ. of Tenn., Knoxville), Bruce Pint (ORNL), Nicholas R. Brown (Univ. of Tenn., Knoxville)

The Molten Salt Thermodynamic Database (MSTDB): A Resource for MSR Design, Development, and Regulation

Theodore M. Besmann, Johnathon C. Ard, Kaitlin E. Johnson, Matthew S. Christian, Jacob A. Yingling (Univ. of South Carolina), Jake W. McMurray (ORNL)

Thermodynamic Insights Into Corrosion in NaCl-LiCl-UCl3-UCl4 Molten Salt

Jacob A. Yingling, Theodore M. Besmann, Johnathon C. Ard, Kaitlin E. Johnson, Matthew S. Christian (Univ. of South Carolina), Jake W. McMurray (ORNL)

Conceptual Design of the Versatile Experimental Salt Irradiation Loop (VESIL) in the Advanced Test Reactor

Abdalla Abou-Jaoude (INL), Sandesh Bhaskar (NC State Univ.), Calvin Downey (INL)

The Effect of Coordination Numbers in Molten Salt Thermodynamic Models

Matthew S. Christian, Johnathon C. Ard, Theodore M. Besmann (Univ. of South Carolina)

Sound Propagation Characteristic of Phononic Crystals Pipeline with Periodic Vibration Isolation Mass

Qingna Zeng, Donghui Wang, Fenggang Zang, Yixiong Zhang, Xiaozhou Jiang (Nuclear Power Institute of China)

NSUF RAD-AFM: Nanoscale Material Property Measurements of Radioactive Materials

Shawn Riechers, Andy Casella, Dave Senor (PNNL), Pradeep Ramuhalli (ORNL)

Preliminary Results from In-Pile Transient Boiling Experiments at the TREAT Facility

C. Jensen, C. Folsom, N. Woolstenhulme, A. Fleming, R. Armstrong, D. Wachs (INL), R. Hernandez, N. Brown (Univ. of Tenn., Knoxville), K. Terrill, R. Christensen (Univ. of Idaho)

Informing Transient Testing of Fuel Designs for the Transformational Challenge Reactor

Robert Kile (Univ. of Tenn., Knoxville), Daniel Schappel, Aaron J. Wysocki, Gokul Vasudevamurthy, Kurt A. Terrani (ORNL), Nicholas R. Brown (Univ. of Tenn., Knoxville)

Strontium Diffusivity in IG-110 Graphite Using a Time-Release Method

Taylor Mae Weilert, Kyle L. Walton, John D. Brockman , Sudarshan K. Loyalka (Univ. of Missouri)

HFIR Irradiation Testing Supporting the Transformational Challenge Reactor

A. G. Le Coq, K. D. Linton, P. Champlin, R. H. Howard, X. Hu, T. S. Byun, K. A. Terrani (ORNL)

Establishing Maximal Core Excess Reactivity Envelope for TREAT Test Vehicle Insertion

John D. Bess, Nicolas E. Woolstenhulme, James R. Parry (INL)

Proton Radiation Effects on the Mechanical and Chemical Characteristics of 3D Printed ABS: Preliminary Results

Arielle J. Miller, Grant M. Warner, Dharmaraj Raghavan (Howard Univ.)

Room-Temperature Electrodeposition of Aluminum Coating from 1-Ethyl-3-Methylimidazolium Tetrachloroaluminate Based Ionic Liquid Bath

Junhua Jiang, Congjian Wang (INL)

Creep Resistance of Additively Manufactured 316 Stainless Steel

Meimei Li, Xuan Zhang, Wei-Ying Chen, Florent Heidet (ANL), T. S. Byun, Kurt A. Terrani (ORNL)

Testing and Evaluation of Additively Manufactured TCR Core Materials

T. S. Byun, M. N. Gussev, B. E. Garrison, J. Simpson (ORNL), M. Li, X. Zhang (ANL), K. A. Terrani (ORNL)

In Situ Mechanical Testing of AM 316L Steel-TCR Core Material

M. N. Gussev, T. S. Byun, R. R. Dehoff, K. A. Terrani (ORNL)

Evaluation of Heat Treatments for Additively Manufactured 316L

J. Simpson, R. Dehoff, T. S. Byun, K. A. Terrani (ORNL)

Modeling Time-Dependent Surrogates of Additive-Manufactured Nuclear Fuels Processes

Congjian Wang, Wen Jiang, Yipeng Gao (INL)

In-situ High-energy X-ray Study of Deformation Mechanisms in Additively Manufactured 316 Stainless Steel

Xuan Zhang, Meimei Li, Jun-Sang Park, Peter Kenesei, Jonathan Almer (ANL)

Optical Transmission of a-SiO2 and α-Al2O3 Following High-Dose Neutron Irradiation

Christian M. Petrie (ORNL), A. Birri, T. E. Blue (The Ohio State Univ.)

High Temperature Silicon-Carbide Furnace for Near Core Irradiation Experiments

Matthew P. Van Zile, Joel Hatch, Andrew Kauffman, Lei R. Cao (The Ohio State Univ.)

Designing an Impedance-based Technique for Studying Corrosion on Cladding Materials

Ling Ding, Hongqiang Hu (INL), Michael Reynolds, Michael F. Hurley, Claire Xiong (Boise State Univ.)

Compensation Scheme for Radiation-Induced Attenuation in Optical Fibers Interrogated Using Low-Coherence Interferometry

Daniel C. Sweeney, Adrian M. Schrell, Christian M. Petrie (ORNL)

In-Pile Loss of Coolant Accident Testing at TREAT

N. Woolstenhulme, C. Jensen, C. Folsom, R. Armstrong, D. Kamerman, D. Wachs (INL)

Computational Analysis of Rhenium (I) Complex

Allison McKee, Meheret Tadesse (Univ. of Houston-Downtown)

Development of Yttrium Hydride Moderator for the Transformational Challenge Reactor

Xunxiang Hu, Chinthaka Silva, Kurt A. Terrani (ORNL)

Rapidly Screening Materials for Void Swelling Resistance with Indirect Photoacoustic Measurements

Nouf Almousa (Princess Nourah Bint Abdulrahman Univ.), Benjamin Dacus, Kevin B. Woller (MIT), Changheui Jang (KAIST), Michael P. Short (MIT)

A Computational Investigation of the Diffusive Pathways for Interstitial Helium in bcc W and bcc Mo

Adib J. Samin (Air Force Institute of Technology)

Development of Cable Aging Acceptance Criteria for Nuclear Facilities

Patrick Ellis, Gary Harmon, Patrick Ward, Codi Ferree (AMS)

Application of Condition Monitoring Technologies for Aging Electrical Cables

Bryan McConkey, Trevor Toll, Patrick Ellis, Elijah Connatser (AMS)

Structural Materials Investigations for the Westinghouse Lead Fast Reactor

Michael R. Ickes, Luke Czerniak, Arash Parsi, Paolo Ferroni (*Westinghouse Electric Co.)

The Impact of Model Parameters and Local Conditions on the Hydrogen Migration and Redistribution Model in Bison

Seokbin Seo, Edward M. Duchnowski, Nicholas R. Brown (Univ. of Tenn., Knoxville)

Performance Analysis of Silicon Carbide Composite Clad Uranium Carbide Fuel during Reactivity Initiated Accident

Hangbok Choi, John Bolin (General Atomics)

Microstructural Analysis of the SiC Layer of Tristructural-Isotropic Particles in High-Temperature Steam Atmospheres

Katherine Montoya, Brian A. Brigham (Univ. of Texas, San Antonio), Tyler J. Gerczak (ORNL), Elizabeth Sooby Wood (Univ. of Texas, San Antonio)

Using Machine Learning to Predict the Oxidation of Graphite

Cole Moczygemba, Michael Geyer, Amanda Fernandez, Elizabeth Sooby Wood (Univ. of Texas, San Antonio)

Analysis of Graphite Matrix Kinetics and Burn-off Products under Off-Normal High-Temperature Gas-Cooled Reactors Conditions

Brian A. Brigham, Katherine I. Montoya (Univ. of Texas, San Antonio), Tyler J. Gerczak (ORNL), Elizabeth Sooby Wood (Univ. of Texas, San Antonio)

Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another

Daniel Schappel, Kurt A. Terrani (ORNL)

Fabrication and Characterization Methodology of Transformational Challenge Reactor Fuel Form

Gokul Vasudevamurthy, Micheal Trammell, Dylan Richardson, Brian Jolly, Andrew Nelson, Grant Helmreich, Austin Schumacher (ORNL), Trevor Smuin (INL), Kurt Terrani (ORNL)

Current Issues in Computational Methods–Roundtable

Robert Grove (ORNL)

Implicit Methods with Reduced Memory for Time-Dependent Boltzmann Transport Equation

Dmitriy Y. Anistratov (NC State Univ.)

Matrix Riccati Equation Method (MREM) of Solution of the Neutron Transfer Equation

B. Ganapol (Univ. of Arizona), J. Patel (The Ohio State Univ.)

A Novel Analytical Nodal Method for Solution of the SN Transport Equation

Joshua Rocheleau, Dean Wang (The Ohio State Univ.)

Improving Convergence via Removal of Scattering Ratio Threshold in Discrete Diffusion Monte Carlo

Alexis Maldonado, Mathew A. Cleveland, Kelly G. Thompson (LANL)

Analysis of Mixed Cell Treatments for Multimaterial Nonlinear Radiation Diffusion

Pedram Ghassemi, Samuel P. Schofield (LLNL)

MPCORE Code for OPR-1000 Transient Multiphysics Simulation with Adaptive Step Size Control

Alexey Cherezov, Hanjoo Kim, Jinsu Park, Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

DAG-OpenMC: CAD-Based Geometry in OpenMC

Patrick C. Shriwise (ANL), Xiaokang Zhang (Chinese Academy of Sciences), Andrew Davis (UK Atomic Energy Agency)

Extending MPACT to 2D Hexagonal Geometry

Kevin J. Connolly, Aaron M. Graham (ORNL)

Application of MATLAB PDE Toolbox for the IAEA-3D PWR Benchmark

Abiodun Ajirotutu, Xue Yang (Texas A&M Univ., Kingsville)

Assessing the Effectiveness of Acceleration Methods for Deterministic Neutron Transport Solvers

J. S. Rehak, R. N. Slaybaugh (Univ. of California, Berkeley)

Stability Analysis of CMFD Acceleration and Linear Prolongation for Weighted Linear Difference Schemes

Rodolfo M. Ferrer (Studsvik Scandpower)

A Hybrid Neutronics Method with Diffusion Synthetic Acceleration for k-eigenvalue Problem

Jiahao Chen, Jason Hou (NC State Univ.)

Hybrid Parallel Computing of Solving 3D Multi-group Neutron Diffusion Equation via Multi-level CMFD Acceleration

Shunjiang Tao, Yunlin Xu (Purdue Univ.)

Bayesian Parameter Estimation of Neutron Multiplicity Counting Equations

Philippe P. Humbert (CEA)

Constrained Sensitivity Analysis for Reactor Physics Problems

Jeongwon Seo, Hany Abdel-Khalik (Purdue Univ.), Zoltan Perko (Delft Univ. of Technology)

NCS Design and Evaluation of New High-density Storage Containers

Amber McCarthy (Consolidated Nuclear Security)

ANSI/ANS-8.7 Applications for the Storage of Criticality Control Overpacks

Brittany M. Williamson (Savannah River Nuclear Solutions)

A Parametric Study of Uranium Sensitivity in an Aqueous Separations Simulation

Camden Blake (Rensselaer Polytechnic Institute), Tracy Stover (Savannah River Nuclear Solutions, LLC)

The Effect of ENDF/B-VIII.0 on Jezebel

Jeffrey A. Favorite (LANL)

Impact of Increased Enrichment on Nuclear Analysis Accuracy Due to Cross-Section Uncertainties

Dale Lancaster (NuclearConsultants.com), Charles T. Rombough (CTR Technical Services, Inc.), Fred H. Smith (EPRI)

Application of Bootstrap Method to Estimated Criticality Lower-Limit Multiplication Factor Considering Nuclear Data-Induced Uncertainty

Takuto Hayashi, Tomohiro Endo, Akio Yamamoto (Nagoya Univ.)

Implementation of Whisper-based Validation at the Hanford Tank Farms

Alyssa Kersting (Washington River Protection Solutions)

Design of a Critical Experiment to Validate Yttrium Hydride at Varying Temperatures

T. Cutler, T. Grove, K. Amundson, H. Trellue (LANL)

Description and Use of SCALE Sampler Parametric Capability for Engineering Analysis and Optimization

W. J. Marshall, T. M. Greene, B. D. Brickner, R. A. Hall (ORNL)

Performing keff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS: Applicable Experiment Selection

W. J. Marshall, J. B. Clarity, K. Banerjee (ORNL)

Performing keff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS: Sensitivity Calculations

W. J. Marshall, J. B. Clarity, K. Banerjee (ORNL)

Criticality Safety Analysis of Fresh Fuel Storage of Barakah Nuclear Power Plant

Shaikha A. AlShamsi, Batool M. Madani, Walid A. Metwally (Univ. of Sharjah)

Review of Recent CSSG Activities–Panel

David Hayes (LANL)

Sharing of Good Industry Practices and/or Lessons Learned in Nuclear Criticality Safety–Panel

Deborah Hill (UK NNL)

Balancing Competition and National Needs in the Medical Isotopes Market–Panel

Joseph Christensen (SHINE Medical Technologies)

ANS-8 Standards Forum

Douglas Bowen (ORNL)

New Developments in Shipping Packages Related to Criticality Safety–Panel

Marvin Barnett

Summary of the Reduction of Severe Accident Uncertainties (ROSAU) Project

J. R. Licht, S. Lomperski, N. Bremer, M. T. Farmer (ANL), S. Basu (US NRC, retired)

Development of Integrated Mechanistic Source Term Assessment Software for Liquid Metal Reactors

Matthew Bucknor, Acacia J. Brunett, James L. Jerden, David Grabaskas, Daniel J. O'Grady, Adam J. Dix (ANL)

Methodology for Selecting Advanced Reactor Licensing Pathways

R. Patrick White (MIT)

Evaluation of Flow Boiling Transient Critical Heat Flux Experiment and Simulation

Soon K. Lee, Nicholas R. Brown (Univ. of Tenn., Knoxville)

Nonlinear Dynamic Explicit Analysis for 2-over-1 Interaction

N. D. Catella, C. H. Roy (SGH)

Nuclear Power Plant Evacuation: Gaps, Strategies, and Activity Scheduling

Adam Stein, Paul Fischbeck (Carnegie Mellon Univ.), Sola Talabi (Pittsburgh Technical LLC), Cristian Marciulescu (EPRI)

Considerations for Environmental Impact Assessment for Small Modular Reactors

G. Martinez-Guridi (IAEA), M. Phaneuf (Canadian Nuclear Safety Commission), M. H. Subki, M. Hussain, F. Reitsma (IAEA)

Potential Improvements in Human Error Probability Seed Optimizer Algorithms

Nathan R. DeKett (Enercon Services)

Projecting Top Event Frequencies using a Pareto Distribution Model

Nathan R. DeKett (Enercon Services)

Flammable Gas Controls on 56 Million Gallons of Radioactive Waste at DOE Hanford

T. Albert Hu, Ph.D.

Managing Hydrogen Systems in Nuclear Facilities: Lessons Learned from the DOE Complex and Industry–Panel

Kevin O'Kula (Amentum)

Meeting the Challenges in Non-LWR PRA Standard Development–Panel

Matthew Denman (Kairos)

Prospects for Blockchain Technology in International Security/Safeguards–Panel

Luc Van Den Durpel

Lessons Learned from NNSA Consortias–Panel

Stefani Buster

Stochastic Analysis for Long Term Capital Structures, Systems, and Components Refurbishment and Replacement

Congjian Wang, Diego Mandelli (INL), David Morton (Northwestern Univ.), Ivilina Popova (Texas State Univ.), Stephen Hess (Jensen Hughes), Shawn St. Germain, Curtis Smith (INL)

Effective Nuclear Plant Waste Heat Utilization by a Bottoming Cryogenic Power Cycle

Alex Kravets, Don Grace (Veritask Energy Systems, Inc.)

IAEA Activities to Facilitate Near Term Deployment of SMRs

Frederik Reitsma, M. Hadid Subki, Gerardo Martinez-Guridi (IAEA)

Multi-Gigawatt-Day Low-Cost Crushed-Rock Heat Storage Coupled to Nuclear Reactors for Variable Electricity and Heat

Charles Forsberg (MIT)

Next-Generation Energy Storage Systems for SBO/ELAP Events

Rahul Jay (The City College of New York), Sanjoy Banerjee, Robert J. Messinger (The City College of New York/CUNY Energy Institute)

Engineering a Voltage Buffer to Improve Offsite Power Reliability Independent of Telemetry or Operator Action

Stephen H. Shepherd (Shepherd Hydricity, Inc.)

Base-Load Light-Water Reactors with Variable Electricity Using Crushed-Rock Heat Storage and Steam Peaking Plant with High-Efficiency Steam Injectors

C. Forsberg (MIT), T. Narabayashi (Tokyo Institute of Technology)

System Efficiency and Dynamic Study of Ca(OH)2/CaO Chemical Heat Pump

Aman Gupta (Univ. of Idaho), Paul D. Armatis (Oregon State Univ.), Piyush Sabharwall (INL), Vivek Utgikar (Univ. of Idaho), Brian M. Fronk (Oregon State Univ.)

Separating Nuclear Reactors from the Power Block with Heat Storage: A New Power Plant Design Option: Workshop Summary

Charles Forsberg (MIT), Piyush Sabharwall (INL), Andrew Sowder (EPRI)

Shielding Analyses for the VENUS Instrument Enclosure

I. I. Popova, F. X. Gallmeier (ORNL)

Assessment of Electrostatic Radiation Shielding Efficacy via Void Area Calculation

Luke Stegeman, Rajarshi Pal Chowdhury (Kansas State Univ.), Matthew L. Lund (Univ. of Utah), Dan J. Fry (NASA Lyndon B. Johnson Space Center), Stojan M. Madzunkov (Jet Propulsion Laboratory), Amir A. Bahadori (Kansas State Univ.)

Dose Analysis for a Neutron Source Driven Subcritical Assembly

Cliff H. Ghiglieri, Jeffrey C. King (Colorado School of Mines)

The US EPA Superfund Radon Vapor Intrusion Screening Level (RVISL) Electronic Calculator

Stuart Walker (US EPA)

Investigation into the Breakdown of Assumptions for 1D Radiation Transport in Air

L. M. Rolison, M. L. Fensin, K. C. Kelley, S. S. McCready (LANL)

First Steps in Scaling Adjoint Response to Areal Density for 1-D Neutron Transport in Air

M. L. Fensin (LANL)

International Platforms to Perform Atmospheric Dispersion Models for Dose Projection

Sanjoy Mukhopadhyay, Phillip Vilar Welter, Stephane Defour (IAEA), Richard J. Maurer, Nate Hoteling (Remote Sensing Laboratory - Joint Base Andrews)

McCAD v1.0L An Improved CAD to MCNP Interface Library

M. Harb, C. Wegmann, U. Fischer (Karlsruhe Institute for Technology)

McCad Plugin Developments for the SpaceClaim Software

Yuefeng Qiu, Ulrich Fischer (Karlsruhe Institute of Technology)

Validation of Radiation Transport Methods for Ball Grid Array Inspection Systems

Michael P. Pfeifer, Nathanael Simerl, Ryan J. Strahler, Jack T. Casburn, Miranda L. Dodson (Kansas State Univ.), John Porter (Honeywell FMT, LLC), Walter J. McNeil, Amir A. Bahadori (Kansas State Univ.)

From CAD to Nuclear Data S/U for Shielding Applications

Bor Kos, Robert E. Grove (ORNL), Ivan A. Kodeli (Jozef Stefan Institute)

Radiation Transport with Moving Geometries and Sources Using DAGMC

Chelsea A. D'Angelo, Paul P. H. Wilson (Univ. of Wisconsin, Madison)

Experience with Automatic CAD to MCNP Model Conversion at ORNL's SNS

Igor Remec, Wei Lu (ORNL)

A Gas-Cooled Water Moderated Thermo-Electric Reactor Concept

Anatoly Blanovsky (Westside Environmental Technology)

Modelling of the HTR-PM Pebble-bed Reactor using OpenMC

Jiankai Yu (MIT), Qiudong Wang, Ding She (Tsinghua Univ.), Benoit Forget (MIT)

Multi-physics Coupling of PROTEUS-NODAL and SAM for MSR Simulation under MOOSE Framework

Gang Yang, Mustafa K. Jaradat, Hansol Park, Won Sik Yang (Univ. of Michigan), Changho Lee (ANL)

The Application of Disk-type Burnable Absorber in the Soluble-Boron-Free ATOM Core

Xuan Ha Nguyen, Seongdong Jang, Yonghee Kim (KAIST)

Neutronics Analysis of Cold Critical KRUSTY Experiments using MCNP and Serpent

Kristin Smith (Texas A&M Univ.), Jesson Hutchinson, Theresa Cutler, Rene Sanchez (LANL), Pavel Tsvetkov (Texas A&M Univ.)

Preliminary Study of Model Predictive Control for Load Follow Operation of Holos Reactor

Sooyoung Choi (Univ. of Michigan), Shai Kinast (Univ. of Michigan/Nuclear Research Center Negev), Volkan Seker (Univ. of Michigan), Claudio Filippone (HolosGen LLC), Brendan Kochunas (Univ. of Michigan)

Linear Stability Analysis of HTR-like Micro-reactors

Doron Sivan (Ben-Gurion Univ. of the Negev/Israel Atomic Energy Commission), Shai Kinast (Nuclear Research Center Negev/Univ. of Michigan), Sooyoung Choi, Volkan Seker (Univ. of Michigan), Erez Gilad (Ben-Gurion Univ. of the Negev), Claudio Filippone (HolosGen LLC), Brendan Kochunas (Univ. of Michigan)

Depletion Analysis of a Micro-Reactor Annular Heat Pipe Fuel Element

Alec Golas, Stephanie Astudillo-Gomez, Subash Sharma (Univ. of Massachusetts Lowell)

MINI-SMR-21 in Once-through Long-lived Fuel Cycle Feasibility Assessment

Gray Chang, Julie Foster (JFoster and Associates), Jim Harrell (Zachry Nuclear)

A Numerical Tool for Space Nuclear Reactor Design based on Molten Salt Reactors (MSRs)

P. Rubiolo (Université Grenoble-Alpes), M. Tano (Texas A&M Univ.), J. Blanco, V. Ghetta, J. Giraud, V. Richard (Université Grenoble-Alpes)

Optimal Sizing of a Micro-Reactor for Embedded Grid Systems

Samuel G. Dotson, Kathryn D. Huff (Univ. of Illinois, Urbana-Champaign)

Minimizing a Class of Azimuthal Power Tilts

James C. Brittingham

Neutronics Benchmark of CEFR Start-up Tests with SuperMC

Bo Chang, Yanting Sun, Bin Li, Qi Yang, Bin Wu (Chinese Academy of Sciences)

UUTR Unit Cell Calculations with PENTRAN (SN) and MCNP6 for Activation Foil Validation Studies

Meng-Jen Wang, Glenn E. Sjoden (Univ. of Utah)

Neutronic Consideration of TREAT Facility Fuel SiC Recladding

John D. Bess, Nicolas E. Woolstenhulme (INL)

Monte Carlo Transient Analysis of C5G7-TD Benchmark 3D Problems Using McCARD

Sang Hoon Jang, Hyung Jin Shim (Seoul Nat'l Univ.)

Advances in MCNP for Reactor Calculations

R. B. Wilkerson, G. W. McKinney, C. J. Josey, M. E. Blood, J. D. Galloway, J. C. Armstrong, H. R. Trellue (LANL)

Single Channel Design Based on Artificial Intelligence for Molten Salt Reactors

Mehmet Turkmen, Kathryn D. Huff (Univ. of Illinois)

Development of FRENDY Nuclear Data Processing Code: Generation Capability of Multi-group Cross Sections from ACE File

Akio Yamamoto, Tomohiro Endo (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency)

Analytic Treatment of Intra-Fuel-Rod Temperature Distributions in the GPU-Based Continuous Energy Monte Carlo Code PRAGMA

Namjae Choi, Han Gyu Joo (Seoul Nat'l Univ.)

Adjoint Driven Ex-Core Response Estimation in PWR with Thermal Feedback

Shane C. Henderson, Tara M. Pandya, Shane Stimpson (ORNL)

A Unified Form of Stabilized Finite Element Methods for Solving the First-order Neutron Transport Equation

Liangzhi Cao, Chao Fang, Hongchun Wu (Xi’an Jiaotong Univ.)

Relaxation of Quasi-Static Approach via Polynomial Interpolation in the Predictor Corrector Quasi-Static Method

T. Oh, Yonghee Kim (KAIST)

Unstructured Mesh-Grid Multi-Physics Analysis with Monte Carlo iMC Code for Advanced Fuel Elements

Hyeontae Kim, Yonghee Kim (KAIST)

Conceptual Safety Design Report for the Versatile Test Reactor

Doug Gerstner, Jason Andrus, Troy Reiss (INL)

From Nuclear Data to Reactor Design

Vladimir Sobes (Univ. of Tenn.),Luiz Leal (Institut de radioprotection et de sûreté nucléaire), Benoit Forget (MIT), Barry Ganapol (The Univ. of Arizona)

Development of Coupled Monte Carlo Transport-burnup and CFD Simulations in SuperMC

Louhanrong Yu (Chinese Academy of Sciences/Univ. of Science and Technology of China), Lei Wang, Bin Wu, Shengpeng Yu, Pengcheng Long (Chinese Academy of Sciences)

Verification of Predicted Energy Deposition Using CASMO5 Coupled Neutron-Gamma Transport Solutions for Selected VERA Benchmark Problems

Rodolfo Ferrer, Joshua Hykes, Charles Wemple (Studsvik Scandpower)

University of Tennessee Fast Neutron Source Design History

J. Wesley Hines, John Pevey, Ondrej Chvala, Vlad Sobes (Univ. of Tenn.)

Advanced Nuclear Engineering to Support Space Exploration

Florent Heidet, Yoichi Momozaki (ANL)

Design Downselection for the Transformational Challenge Reactor

B. R. Betzler, B. J. Ade, A. J. Wysocki, P. C. Chesser, M. S. Greenwood, P. L. Wang, N. D. See, X. Hu, K. A. Terrani (ORNL)

Power Level Downselection for the Transformational Challenge Reactor

B. R. Betzler, B. J. Ade, A. J. Wysocki, P. K. Jain, M. S. Greenwood, J. D. Rader, J. J. W. Heineman (ORNL), R. F. Kile, N. R. Brown (Univ. of Tenn., Knoxville), K. A. Terrani (ORNL)

Control Element Design for the Transformational Challenge Reactor (TCR)

J. R. Burns, B. R. Betzler, B. Ade (ORNL), F. Heidet, A. Bergeron (ANL)

Transformational Challenge Reactor Moderator Material Selection to Achieve Fuel Minimization

A. Bergeron, P. Vegendla, S. Mohanty, F. Heidet (ANL), B. J. Ade, B. R. Betzler (ORNL)

Thermal Neutron Scattering Measurements of YHx for the Transformational Challenge Reactor

Chris W. Chapman, Xunxiang Hu, Jesse Brown, Goran Arbanas, Alexander I. Kolesnikov, Yongqiang Cheng, Luke Daemen (ORNL)

Application of Motion Primitives to Train Robotic Behaviors for Nuclear Facility D&D

Young Soo Park, Jonathan Bayert, Dongjune Chang (ANL), Sungmoon Joo, Jonghwan Lee (KAERI)

A Drone-Based Automated Radiation Surveillance System

Abdulrahman M. Riyadha, Ahmad M. Elshoubaky, Jamil A. Rihani, Mohammad A. Al-Shabi, Walid A. Metwally, Bassam A. Khuwaileh (Univ. of Sharjah)

Evaluation of Pressure Drop Correlations for the Wire-wrapped Rod Bundles

Su-Jong Yoon (INL), Florent Heidet (ANL)

Sodium-Cooled Reactor Fuel Assembly Hydraulic Holddown

Earl E. Feldman (ANL)

Experimental Quantification of Form Drag on Rising Bubbles Using PIV

Alexander Duenas, Isaiah Wieland, Wade Marcum, Qiao Wu (Oregon State Univ.)

Design of a Pebble Bed Heat Transfer Separate Effects Test

Jacob Uselman, Izabela Gutowska, Joshua Halsted, Shikha Kumar, Connor Dionne, Brian Woods (Oregon State Univ.), Nicolas Zwiebaum, Kyle Brumback (Kairos Power, LLC)

Investigation of the influence of the bundle geometry distortion on the critical heat flux

D. A. Oleksyuk, D. R. Kireeva, L. L. Kobzar (NRC Kurchatov Institute)

Design and Verification Testing for Metallic Fuel Relocation Experiments with Pressure Injection in a Pin Bundle Core Structure of a Sodium-Cooled Fast Reactor

Taeil Kim, Dzmitry Harbaruk, Darius Lisowski, Nathan Bremer, Mitchell Farmer, Christopher Grandy, Yoon Il Chang (ANL)

Measurements of Pressure Drop in Pipes with Twisted Tape Inserts for Molten Salt Reactor Applications

Cody S. Wiggins, Arturo A. Cabral, Meryem E. Murphy, Candler L. L. Langston, Lane B. Carasik (Virginia Commonwealth Univ.)

Gas Dispersion Analysis for Glovebox Accident in a Ventilated Process Room

Si Y. Lee, Richard A. Patterson (Savannah River Nuclear Solutions)

Modelling Loss of Flow Transients in Gallium Thermal-hydraulic Facility Using Systems Code SAS4A/SASSYS-1 and Using CFD

Sundar Namala, Rizwan-uddin (Univ. of Illinois, Urbana-Champaign), Tyler Sumner (ANL)

CFD Modeling of NBSR Thermal Shield

Manikanta Grandhi, Xue Yang (Texas A&M Univ., Kingsville)

Probing Interfacial Momentum Closures in Two-phase Bubbly Flow with Machine Learning-aided Methods

Han Bao (INL), Jinyong Feng (MIT), Hongbin Zhang (INL), Nam Dinh (NCSU)

Validation of the 1-D Thermal Stratification Model in Gallium Environment

Cihang Lu, Zeyun Wu (Virginia Commonwealth Univ.), Brendan Ward, Hitesh Bindra (Kansas State Univ.)

Cooling Channel Optimization in Additively Manufactured Gas-Cooled Reactor Core

Justin Weinmeister, Prashant K. Jain

Multi-Scale & Multi-Physics Analysis of PWR Steam Line Break Accident

Jae Ryong Lee, Ik Kyu Park, Han Young Yoon (KAERI)

Sodium Fire Models for In- and Ex-vessel Safety Analysis Code SPECTRA

Mitsuhiro Aoyagi, Akihiro Uchibori, Takashi Takata, Hiroyuki Ohshima (Japan Atomic Energy Agency)

Code Validation for SBLOCA Test of PHWR using MARS-KS

Kyunglok Baek, Seon Oh Yu (Korea Institute of Nuclear Safety)

Improvement of Advanced Nuclear Reactor Safety Analysis Codes Using CFD

Rohan Biwalkar, Sola Talabi (Pittsburgh Technical LLC), Kenneth Redus (Redus and Associates LLC)

CFD Modeling of Hot-Channel for Potential High-Power Configuration of Missouri S&T Reactor

Thaqal Alhuzaymi (King Abdulaziz City for Science and Technology), Ayodeji B. Alajo, Joshua Schlegel (Missouri Univ. Science and Technology)

Study on Selecting Conservative Axial Power Shape for DNBR Design Limit

Shane Park (KEPCO Nuclear Fuel)

Theoretical Exploration of Heat Transfer Characteristics of Liquid Metals

Yaou Shen, Shinian Peng, Mingyu Yan, Yu Zhang, Jian Deng (Nuclear Power Institute of China)

CFD Analysis of PRHR-Heat Exchanger Using Euler Multiphase Model

Soumitra Vadnerkar, Xue Yang (Texas A&M Univ., Kingsville)

Artificial Intelligence-based Phase-Change Regime Classification of Acoustic Emission Detection in Pool Boiling

Do Yeong Lim, In Cheol Bang (Ulsan Nat'l Institute of Science and Technology)

Microreactor Safety Analysis: Requirements, Considerations and Potential Impact

Rohan Biwalkar, Sola Talabi (Pittsburgh Technical LLC), Kenneth Redus (Redus and Associates LLC)

Assessment of the Thermal-Structural Characteristics of Core Components in a Preconceptual Design of the Transformational Challenge Reactor

Casey J. Jesse, James W. Sterbentz (INL), Benjamin R. Betzler (ORNL)

Design of a Flat Channel Experiment to Study Molten Salt Thermal Radiation Heat Transfer

P. Rubiolo, J. Giraud, V. Ghetta, M. Tano, J. Blanco, F. Kovacevich (LPSC, Université Grenoble-Alpes)

Challenges and Opportunities in Thermal Hydraulics of High Temperature Gas Cooled Reactors–Panel

Brian Woods (Oregon State)

Innovating Nuclear through an Entrepreneurial Student Prize Competition

Timothy Crook (MCR Performance Solutions)

Communicating Safety & Risk to the Public

Timothy Crook (MCR Performance Solutions)

Carbon pricing and clean energy standards 101

Timothy Crook (MCR Performance Solutions)

Leadership styles & management techniques

Timothy Crook (MCR Performance Solutions)

Pitch your Job

Timothy Crook (MCR Performance Solutions)

Resume/CV Workshop

Timothy Crook (MCR Performance Solutions)