Winter Meeting 2019 / Volume 121

Table of Contents

Author Index

Full Issue

Opening Plenary

Jeffery Brault (Consultant)

ANS President's Special Session

Marilyn Kray (Exelon)

General Chair's Special Session

Jeffery Brault (Consultant)

[ANS Nuclear Grand Challenge] Advanced Material Testing Using Accelerators–Panel

Reginald Ronningen (Michigan State)

Primary Knock-on Atoms for Accelerator Facilities: Simulations and Experimental Design

Pi-En Tsai, Yosuke Iwamoto (JAEA), Masayuki Hagiwara (High Energy Research Org.)

Development of a Non-Destructive Structural Health Monitor for Accelerator Components

G. L. Solbrekken (Univ. Missouri), N. Gazis (European Spallation Source), G. Manoharan (Univ. Missouri)

Simulations of Vertical GaN Diode Performance Under Electron Beam Radiation Exposures

Matthew J. Jasica, William R. Wampler, Barney L. Doyle, Greg W. Pickrell, William Cowan, Albert Colon, Michael Van Heukelom, Caleb E. Glaser (Sandia)

Molybdenum-99 Production via Fissile Solution Reactor and Electron Beam Accelerator

Kelley Verner (LANL, Univ. Idaho), Seung Jun Kim (LANL)

Recent Progress on the Phoenix Accelerator-Based Intense Fusion Neutron Source

Ross Radel, Tye Gribb, Arne Kobernik, Chris Seyfert, Logan Campbell, Preston Barrows (Phoenix LLC.)

Nonproliferation Features of the Mu*STAR Subcritical Molten-Salt Accelerator-Driven Reactor

Mary Anne Cummings, Rolland P. Johnson, Thomas J. Roberts (Muons Inc.)

Capture of Decay Heat to Produce Thrust in a Nuclear Propulsion Rocket

William G. Culbreth, Kimberly Gonzalez (UNLV)

A Pathway for Fully Ceramic Microencapsulated (FCM) Fuels in Nuclear Thermal Propulsion (NTP)

Caen Ang (U.T., Knoxville), Lance Snead (Stony Brook Univ.), Alex Gordon (U.T., Knoxville), Kelsa Benensky (NASA), Sam Judd (USNC-Space), David Sprouster (Stony Brook Univ.), Yutai Kato (U.T., Knoxville).

Gas Tilt-Pad Bearing Performance in a Supercritical CO2 Brayton Cycle for HTGR for Space Applications

Nathan Colgan, Mark Anderson, Gregory Nellis (U.W., Madison), Ken Cragin (Creare LLC)

Thermoelectric Characteristics Analysis of TOPAZ-II

Zhiwen Dai, Chenglong Wang, Xiao Liu, Dalin Zhang, Suizheng Qiu, Guanghui Su (Xi'an Jiaotong Univ.)

Numerical Investigation on Heat Transfer Characteristics of Helium-Xenon Gas Mixture

Hao Qin, Chenglong Wang, Suizheng Qiu (Xi'an Jiaotong Univ.)

One-Way Coupled Tumor Response Model for Combined-Hyperthermia-Radiotherapy Treatment with Anisotropic Scattering

Japan K. Patel, John J. Kuczek, Richard Vasques (Ohio State)

Integrating Backscatter X-Ray Imaging with Super-Resolution Imaging Algorithms for Plant Phenotyping

Jyothier Kumar Nimmagadda, Shuang Cui, Jose F. Ruiz-Munoz, Alina Zare, James E. Baciak (Univ. Florida)

The Path Towards a Low-Carbon Sustainable Energy Supply System–Panel—II

Frank Carre (CEA), William Hannum (Consultant)

Overview of the Various Environmental Standards Projects–Paper/Panel

Leah Parks (NRC)

Technical Issues Addressed in 2019 Revision of ANS 16.1

W. L. Ebert (ANL), L. Parks (U.S. NRC)

Integrated Energy Systems: Integrating Nuclear Plants with Renewable Sources Through Alternative Applications Beyond the Grid–Panel

Leah Parks (NRC)

Development of New Equipment for Recovering Old Nuclear Wastes

Aurélie Ithurbide, Roger Serrano, Jean-Claude Masy

Developing a Procedure of Safety Assessment for Decommissioning Activities

Ken-ichi Tanaka (Intitute of Applied Energy), Isao Yamaoka, Takashi Muramatsu (Japan Nuclear Safety Institute)

Lessons Learned Pave Paths for the Future

Glenn S. K. Williams, Allen C. Church (FMI Energy Holdings)

Equilibrium Calculations for HyBRID Decontamination Systems

Byung-Chul Lee (Hannam Univ.), Jei-Kwon Moon, Seon Byeong Kim (KAERI)

Blending Simulation of On-Site Waste Treatment for Kori-1 Bioshield Decommissioning Concrete

Eui Taek Lee, David S. Kessel, Chang-Lak Kim (KEPCO)

Equilibrium Calculations in HyBRID Decontamination of Nickel Ferrite and Chromite

Jei-Kwon Moon (KAERI), Byung-Chul Lee (Hannam Univ.), Seon-Byung Kim (KAERI)

Advanced and Innovative Technologies for Decommissioning of Nuclear Facilities and Environmental Remediation of Radiological Contamination–Panel

Boby M. Abu-Eid, Leah Parks (NRC)

International Decommissioning–Paper/Panel

James Byrne (Byrne & Associates)

The Decommissioning and Waste Management programme of the Joint Research Centre of the European Commission

Stéphane Brémier, Vincenzo Rondinella, Paolo Peerani, Francesco Basile, Riccardo Casale (European Commission)

Fusion-Fission Hybrid Reactor for Waste Transmutation

Yerkebulan Ali, Brian Arko, Jonathan Karpesky, Adam Parler, Jeffrey King (Colorado School Mines)

Design of a Zirconium Critical Benchmark

Ngai To Yu, Chad Meece, Robert Jacob, Gabriella Bruno, Ryan O’Neill (RPI)

Equilibrium Core Design of a NuScale Designed Small Modular Reactor Using CASL’s Virtual Environment for Reactor Applications (VERA)

M. Hines, M. Underwood, A. Naylor, M. Burrell, L. Clowers, K. Knecht, G. I. Maldonado (U.T., Knoxville)

Design of the Molten Salt Nuclear Battery (MSNB)

Eugene Engmann, John Peterson, James Richards, Derreck Blight, Winfred Sowah, Joseph Warner (Univ. Idaho)

Synthesis of the First All-Uranium(V) Borate

Kristen Pace, Vancho Kocevski, Hans-Conrad zur Loye (Univ. South Carolina)

Incorporating Variable Moderation Elements into the FHR Design to Increase Both Cycle Length and Discharge Burnup

Vedant Mehta (LANL, Georgia Tech.), Dan Kotlyar (Georgia Tech.)

Overstepping L?wenstein’s Rule: A Route to Unique Uranium Aluminophosphate Frameworks

Christian A. Juillerat, Vladislav V. Klepov, Hans-Conrad zur Loye (Univ. South Carolina)

Photopolymerized Plastic Scintillators Capable of Neutron and Gamma Ray Discrimination

Allison Lim, Adam C. Mahl, Joseph Latta, Henok A. Yemam, Uwe Greife, Alan Sellinger (Colorado School of Mines)

Bis-(2-ethylhexyl) Phosphoric Acid Functionalized Carbon Nanoparticles for Chromatographic Lanthanide Separations

Erin R. Bertelsen, Brian G. Trewyn, Jenifer C. Shafer (Colorado School Mines)

An Overview of Methodologies for Cybersecurity Vulnerability Assessments Conducted in Nuclear Power Plants

John Peterson?, Michael Haney, R. A. Borrelli (Univ. Idaho)

In-Pile OFDR Sensing with Fiber Bragg Gratings in Sapphire Optical Fiber

Kelly M. McCary (INL, Ohio State), Brandon Wilson (ORNL), Joshua Daw, Pattrick Calderoni (INL), Christian Petrie (ORNL), Thomas Blue (Ohio State)

Focus on Communications—I—Communicating with Policy Makers–Panel

Mimi Limbach (Potomac Communications)

Focus on Communications—II—Meet the Media–Panel

Laura Hermann (Potomac Communications)

Thermal Stratification Study in a Liquid Sodium Experimental Facility

James Schneider, Mark Anderson (U.W., Madison)

Validation Experiments for Annular linear Induction Pump

Mohammed Shutayfi, Josh Morsell, Anant Raj, Steven Shannon, Jacob Eapen (NCSU)

Can an Analytical Model be Employed for Simulating Used Fuel Vacuum Drying Process?

Sudipta Saha, Amitav Tikadar, Travis W. Knight, Jamil A. Khan, Tanvir I. Farouk (Univ. South Carolina)

CFD Framework for Used Fuel Vacuum Drying Application

Amitav Tikadar, Sudipta Saha, Travis W. Knight, Tanvir I. Farouk, Jamil A. Khan (Univ. South Carolina)

Distributed Wall Temperature Measurements in a Scaled Water-Cooled RCCS

David Holler, Rodolfo Vaghetto, Yassin Hassan (Texas A&M)

Creep-Fatigue Deformation of an Advanced Austenitic Stainless Steel (Alloy 709)

Zeinab Y. Alsmadi (NCSU), Abdullah S. Alomari (King Abdullaziz City), N. Kumar (Univ. Alabama), K. L. Murty (NCSU)

Evaluation of Surface Characteristics of FeCrAl Alloy Accident Tolerant Fuel Cladding Material After Critical Heat Flux Testing Under Atmospheric Pressure

Rajnikant Umretiya, Robert Uhorchuk (VCU), Mark Anderson, Barret Elward (U.W., Madison), Sama Bilbao y Leon (VCU), Raul B. Rebak (GE), Jessika Rojas (VCU)

Exploratory Study into the Effectiveness of Active Monitoring Techniques

Arvind Sundaram, Hany S. Abdel-Khalik (Purdue), Oussama Ashy (WSC Inc.)

Diffusion of Silver and Ruthenium Fission Products in Virgin Nuclear Graphite

Kevin R. Graydon, Mikhail Klimov, Edward Dein, Kevin R. Coffey, Yongho Sohn (Univ. Central Florida)

O?-Site Dose Prediction for Decision Making Using Recurrent Neural Networks

Bing Zha, Alper Yilmaz, Tunc Aldemir (Ohio State)

Oxidation E?ects of Air and Steam Ingress on Material Properties of Graphite in HTGRs

Connor Medlen, Hitesh Bindra (Kansas State)

Development of CosMuse: An Integrated Nuclear Power Plant Full Scope Simulation Platform

Shen Mengsi (SJTU), Liyankai, Lingmeng (SJTU, State Power Investment Corp.)

Application of cosFlow and cosKind-R in Nuclear Power Plant Simulation

Cao Ying, Wang Xu (SJTU), Lin Meng (SJTU, State Power Investment Corp.)

Development of a New Experimental Course in Nuclear Engineering

E. Blain, Y. Danon (RPI)

Internet Reactor Laboratory (IRL): Nuclear Engineering Education Utilizing the PULSTAR Reactor

S. A. Lassell, A. I. Hawari (NCSU)

A PhD Distance Learning Program: A Unique Educational Collaboration with the University of Texas and Los Alamos National Laboratory

Sheldon Landsberger, William Charlton, Kevin. Clarno (U.T., Austin), Dan Boravino, Jonathan Mace, Tammy Diaz (LANL)

A Critique of Literature on Transgender Inclusion in Engineering Education and Practice

Emory Colvin, Todd S. Palmer (Oregon State)

Lessons Learned form a Nuclear Materials Security Workshop

Braden Goddard, Manit Shah, Cody Lloyd, Michael Cartwright, Justin Bresson (Virginia Commonwealth), Mike Engelsman (Mirion Technol.)

The NuScale Ambassador Program: Training Employees to Engage with the Public

Lenka Kollar (NuScale)

Benefit and Challenge of Introducing Innovative Ways of Learning Nuclear Engineering at the ENSMR Engineering School

Oum Keltoum Aziza Bouhelal (Higher National School of Mines-Rabat)

Recognizing and Arresting Declining Performance (Indicative of Column 4 Performance)

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

Hammer: An Educational and Research Platform for Neutral Particle Transport Code Development

Evan S. Gonzalez, Aaron G. Tumulak, Kyle A. Beyer, Eric J. Pearson, Matan G. Gottesman, Arav K. Agarwal, Darian J. Fortner, Frank A. Angers, Divans Beqi, Lauren Green, Braden J. Saltus, Brian C. Kiedrowski (Univ. Michigan)

A Picture is Worth a Thousand Words and an Experiment is Worth Fifty Slides: Development of Experiments in Health Physics to Reinforce Basic Radiation Protection Concepts

Sheldon Landsberger, Tracy Tipping, Lawrence Hall, William Charlton (U.T., Austin)

ABET Accreditation Changes: Transition and Implementation–Panel

Walid Metwally (Univ. Sharjah), Youssef Shatilla (Khalifa Univ.)

Comparative Cost Analysis for Disposal of DPCs Relative to Repackaging

Abdelhalim Alsaed (Enviro Nuclear Services), Ernest Hardin (Sandia)

Criticality Analysis for Direct Disposal of Dual-Purpose Canisters

Justin B. Clarity, Kaushik Banerjee, Henrik Liljenfeldt, Paul Miller, John M. Scaglione (ORNL)

Development of Terrenus: A Multiphysics Code for Spent Nuclear Fuel Canister Criticality Analysis

Gregory G. Davidson, Seth R. Johnson, Stylianos Chatzidakis (ORNL)

Consequences of Nuclear Criticality in Dual Purpose Canisters After Disposal

Laura Price (Sandia)

Initial Development of a TH Model for Disposal of 37 PWR Dual-Purpose Canister in Alluvium

Scott L. Painter, Zhufeng Fang, Rob Howard, Kaushik Banerjee (ORNL)

Dual Purpose Canister Filling Demonstration

Nesrin O. Cetiner, Eliott J. Fountain, Venugopal K. Varma, Elvis E. Dominguez-Ontiveros, Kaushik Banerjee (ORNL)

Progress Toward the Development of Cement Fillers for Dual Purpose Canisters

Mark J. Rigali (Sandia), Mark L. F. Phillips (PRRC), Patrick D. Burton, Eduardo Basurto, Ernest L. Hardin (Sandia)

Dual Purpose Canister Heating Evaluation for Casting of High Temperature Fillers

Emilian Popov, Kaushik Banerjee (ORNL)

Demonstration and Feasibility Analyses of Using the Dual-Purpose Canister Drain Pipe to Support the Filling Process

Elvis Dominguez-Ontiveros, Kaushik Banerjee (ORNL)

Options for Modifying Existing and Future DPCs for Disposal

Ernest Hardin (Sandia), Abdelhalim Alsaed (Enviro Nuclear Services), Branko Damjanac (Itasca Consulting Group)

Fuel Cycle Updates from a Regulatory Perspective–Panel

Sven Bader (Orano)

Progress in Consolidated Interim Storage and Next Steps–Panel

Sven Bader (Orano)

Used Fuel and High-Level Waste Management—Einstein’s Definition of Insanity?–Panel

Steven Nesbit (LMBT Consulting)

Study on Radionuclide Dispersion for Accident Condition of Spent Fuel Highway Transport

Chun-hua Chen, Li-wei Chen, Xiao-lei Zheng, Jin Wang, Fang Wang (FDS)

Characterization and Drying of Oxyhydroxides for Dry Storage of Aluminum-Clad Spent Fuel

Matthew Shalloo (Univ. South Carolina), Roderick Fuentes, Anna d’Entremont, Robert Sindelar (SRNL), Travis W. Knight (U.T., Knoxville)

Safeguards Approaches for Remote Monitoring System of Spent Nuclear Fuel Dry Cask Storage

Athena Sagadevan, Sunil Chirayath (Texas A&M)

Development of Sensor Transport System with Tunable Magnetic Wheel

So-Hee Park, Along Wang, Young-Woo Park, Myunggyu D.Noh (Chungnam Naitonal Univ.)

Electrochemical Behavior of Tellurium Species in LiCl-KCl Molten Salts

Brandon Day, Nikunja Shrestha, Vivek Utgikar, Krishnan S. Raja (Univ. Idaho), Guy Fredrickson, Steven Frank (INL)

Redox Behavior of Iodide Species in LiCl-KCl at 450 – 550 °C

Nikunja Shrestha, Brandon Day, Vivek Utgikar, Krishnan S. Raja (Univ. Idaho), Guy Fredrickson, Steven Frank (INL)

Magnetic Field Effects on the Electrochemical Behaviors of Ce in LiCl-KCl Molten Salt

Wentao Zhou, Xubo Gu, Dezhong Wang (Shanghai Jiao Tong Univ.)

Electrochemical Deposition of Fission Products into Liquid Metals from Molten Salts

Hojong Kim (Penn State)

Understanding Thermodynamic Phase Diagrams of Molten Salt Systems via Decision Tree Regression

Miroslava Dobro?ová (VCU, Slovak Univ. Technol.) Dimitris Killinger, Supathorn Phongikaroon (VCU)

Development of ORIGEN Reactor Data Libraries for Thermal Molten Salt Reactors

Kyle Anderson, Steven Skutnik (U.T., Knoxville)

Applicability of the (?,n) Source Term as a Viable Safeguards Measurement for Electrochemical Reprocessing

Stephen N. Gilliam, Jamie B. Coble, Steven E. Skutnik (U.T., Knoxville)

Plutonium Diversion Effect on Molten-Salt Reactor Dynamics

Alexander M. Wheeler, Kyle Anderson, Ondrej Chvála, Steven Skutnik (U.T., Knoxville)

Redox Potential Control for the Molten Salt Reactor Concept

Robin V. Roper, Richard Christensen (Univ. Idaho)

Reclassification of High-Level Waste Under Existing Standards

Jonathan F. Wing (U.T., Knoxville)

Evaluation of an Integrated Iodine Scrubber and Polishing Bed System

R. T. Jubin, S. H. Bruffey, J. A. Jordan (ORNL)

Preparation and Characterization of Epoxy Solidification

Seonggon Ryu, Misuk Jang, Seoung Rae Kim (NESS Co. LTD.)

Parametric Optimization of TRU Destruction Rates in HTR Cores Using Genetic Algorithms and Regression Methods

Takanori Kajihara, Pavel V. Tsvetkov (Texas A&M)

BWR Fuel Bundle Optimization Based on Three-Dimensional Fuel Rods

Brian Andersen (NCSU), David Kropaczek (ORNL), Jason Hou (NCSU)

Neural Network Approach to Model Mixed Oxide Fuel Cycles in Cyclus, a Nuclear Fuel Cycle Simulator

J. W. Bae, B. R. Betzler, A. Worrall (ORNL)

IAEA Project on Research Reactor Spent Fuel Management Options

Frances M. Marshall (IAEA)

An In-Line Neutron Coincidence Counter for Plutonium Mass Quantification

Cole Thompson (U.T., Austin, LANL), Brian O'Neil (LANL), William S. Charlton (U.T., Austin, LANL)

Flibe Fusion Blankets and Flibe Fluoride-Salt-Cooled High-Temperature Reactors: Opportunities for Synergistic Development Strategies

Charles Forsberg, Emilio Baglietto, Matteo Bucci, Ronald G. Ballinger (MIT)

Critical Thermonuclear D-T Fusion in Stimulated LiD Core with Shockwaves

Yasser R. Shaban (HUA Star Technol.), George H. Miley (Univ. Illinois)

Nanoscale Feature Implications on Electron Emission and Gas Breakdown

Amanda M. Loveless, Adam M. Darr, Russell S. Brayfield II, Jacqueline R. Malayter, Sarah A. Lang, Allen L. Garner (Purdue)

Practical Considerations for Intermittent Fault Detection in Nuclear Power Plant Circuits

Bryan McConkey, Trevor Jones, Phil Zarb, Brent Shumaker (Analysis and Measurement Services Corp.)

Nuclear Power Plant Parameter Prediction Strategy for Human Error Detection

Junyong Bae, Seung Jun Lee (UNIST)

Abnormal State Diagnosis Considering Noise Using Grate Recurrent Unit Network

Ji Hyeon Shin, Jae Min Kim, Seung Jun Lee (UNIST)

Improved Explicability for Pump Diagnostics in Nuclear Power Plants

Andrew T. Young, Graeme M. West, Blair D. Brown, Bruce Stephen, Stephen D. J. McArthur (Univ. Strathclyde)

A Calibration Method for Raman Distributed Temperature Sensor in Nuclear Power Plant

Meiqiong Xiang, Yanyang Liu, Xianguo Qing, Jialiang Zhu, Qian Wu, Biwei Zhu, Sijie Xu (Nuclear Power Inst. China)

High Flux Neutron Detection Using Silicon Carbide from Near-core Locations

Praneeth Kandlakunta, Chuting Tan, Nathan Smith, Sha Xue, Neil Taylor (Ohio State), R. Gregory Downing, Vasil Hlinka (AwareAbility Technologies), Lei R. Cao (Ohio State)

A Novel Waveguide Concept for Ultrasonic Thermometry Applications

Nesrin O. Cetiner, Sacit M. Cetiner, Michael J. Roberts, Venu K. Varma, Govindarajan Muralidharan, Thomas R. Muth, Rose A. Montgomery (ORNL)

Wireless Signal Transfer Application of LVDT in Nuclear Reactors

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

Optimization Study for an Eddy Current Flow Meter

Kellen M. Oleksak (ORNL, U.T., Knoxville), Sacit M. Cetiner (ORNL), Aly Fathy, (U.T., Knoxville)

Novel Neutron-Alpha-Fission Radiation Monitoring Technology Using Tensioned Metastable Fluid Detectors

R. P.Taleyarkhan (Purdue), B. Archambault (Consultant), A. Sansone, N. Boyle, M. Hemesath (Purdue_

Gamma Irradiation of Novel Optical Glasses at Elevated Temperature

H. A. Qiao, M. K. Murphy, B. J. Riley (PNNL), J. R. Roth, S. W. Martin (Iowa State), J. Ballato (Clemson)

An FPGA-Based Framework for Digital Nuclear Pulse Processing

E. Dewey, S. Saxena, B. A. Fallin, A. I. Hawari (NCSU)

Pressure Sensing Line Blockage and Degradation in Nuclear Power Plants

Greg W. Morton, Brent D. Shumaker, Dan E. McCarter, H. M. Hashemian (Analysis and Measurement Services Corp.)

Adapting Approximate Entropy as a Health Indicator for Rotating Machinery in Nuclear Power Plants

Cody M. Walker, Jamie B. Coble (U.T., Knoxville)

Investigating Sensor Location Effect on the Accuracy of Cross Correlation Flow Estimation with Coolant Injection Using CFD Simulations

Xiong Gao, J. Wesley Hines, Jamie B. Coble (U.T., Knoxville), L. B. Carasik (VCU)

Radiation Dose Correlation Analysis of Distributed Measurements Using Fiber Optic Intrinsic Sensors

Charles Stratton, Pavel Tsvetkov (Texas A&M)

Scalable Multi-Agent Adaptive Resolution Tools for Collaborative Outage Management

Anirudh More, Nathan Lau (Virginia Tech), Shilo Anders (Vanderbilt)

An Intelligent Operator Support System for Early State Emergency Operations in Nuclear Power Plants

Jung Sung Kang, Jeeyea Ahn, Seung Jun Lee (UNIST)

Bench-Scale Demonstration of a Capacitive Sensor for In-Pile Materials Monitoring

Tyler Naughton (U.T., Knoxville), Christian Petrie (ORNL), Jamie Coble (U.T., Knoxville)

Digital I&C Upgrades–Panel

Edward Quinn (Technology Resources)

Demonstration of Integrated Hazard Analysis for Digital Reactor Trip Systems

Tate Shorthill (Univ. Pittsburgh), Han Bao, Hongbin Zhang (INL), Heng Ban (Univ. Pittsburgh)

Automated Exhaustive Test Case Generation for Safety-Critical Software

Sang Hun Lee (RPI), Seung Jun Lee (UNIST), Sung Min Shin (LAERI), Eun-chan Lee (Korea Hydro & Nuclear Power), Hyun Gook Kang (RPI)

Development of an Obsolescence Cost Model for Nuclear Power Plants

Michael D. Muhlheim (ORNL), Paul J. Hunton (INL), Peter A. Sandborn (Univ. Maryland), Edward L. Quinn (Technol. Resources), Richard E. Hale (ORNL), Robert T. England (INL)

Advanced Diverse Protection System Features for CCF + Large Break LOCA in Advanced Power Reactor 1400

Jin kwon Jung, Yoon Hee Lee, Hyeong Pyo Hong, Jae Hee Yun (KEPCO)

Online Monitoring Technologies for Instrumentation and Control (I&C) Systems in Nuclear Facilities–Panel

Brent Shumaker (AMS)

Application of Control Process Variables for Cyber Attack Detection and Diagnosis in NPPs

Chanyoung Lee, Poong Hyun Seong (KAIST)

Communication in a Nuclear Facility with Elastic Waves Excited with Ultrasonic LiNbO3 Transducers on Pipes

Alexander Heifetz (ANL, IIT), Xin Huang, Dmitry Shribak (ANL, Univ. Chicago), Sasan Bakhtiari (ANL), Jafar Saniie (IIT), Richard Vilim (ANL)

Lessons Learned about Network Defenses of Nuclear Power Plants: A Critical Analysis of Internal Cyberattacks

Brandyn M. Campos, Miltiadis Alamaniotis (U.T., Austin)

Enhancing the Resilience of Key Equipment to False Data Injection Attacks in NPPs

Fan Zhang, Trentin Payne, J. Wesley Hines, Jamie Coble (U.T., Knoxville)

Malware Detection in Critical Infrastructures Using the Electromagnetic Emissions of PLCs

Constantinos Kolias, R. A. Borrelli (Univ. Idaho), Daniel Barbara, Angelos Stavrou (George Mason)

Advances in Nuclear Cybersecurity Research and Development–Panel

Fredrick McCrory (SNL)

Preliminary Study on Using Neutron Generators in Capture Therapy

Walid A. Metwally, Yumna A. Alharahsheh, Entesar Z. Dalah (Univ. Sharjah), Husam Al-Omari (Abu Dhabi Polytechnic)

Mo-99 Production via DT Fusion Driven Subcritical Assembly

Ross F. Radel (Phoenix LLC), Greg R. Piefer, Tracy E. Radel (SHINE Medical Technologies)

Neck Shim Reactivity Worth in the Advanced Test Reactor

Nathan Manwaring (INL)

Application of Neutron-Gamma Technologies in Agriculture

A. Kavetskiy, G. Yakubova, S. A. Prior, H. A. Torbert (USDA)

An Extended-Temperature, Volumetric Source Model for Betavoltaic Power Generation

Andrew O’Connor, Michele V. Manuel (Univ. Florida), Harry Shaw (NASA)

Detection Methodology of Position-Dependent Neutron Energy Using a Threshold Detector Array

Jiseok Kim (KAERI, Hanyang Univ.), Han Rim Lee (KAERI), Yongkyun Kim (Hanyang Univ.)

Design and Optimization of a Pinhole Collimator for a High Resolution Emission Gamma Ray Tomography System Using a Pixelated CZT Detector

Seth Kilby, Joseph Graham (Missouri Univ. Sci. & Technol.)

Investigation of FPGA Based Real Time Processing in Neutron Imaging

A. Datta, A. Kurtz, B. A. Fallin, A. I. Hawari (NCSU)

Modeling and Analysis of an X-ray Imaging Facility at the Colorado School of Mines

Russell Jarmer, Jameson Hetrick, Jesus Mendoza, Jeffrey C. King (Colorado School Mines)

Development of an Imaging Method for Bulk Scintillator Materials

D. Trimas, M. Burger, K. Ogren, I. Jovanovic (Univ. Michigan)

Active Interrogation Using AmBe Directional Source and PGNAA

Kyle M. Paaren, Seth M. Kilby, Hyoung K. Lee (Missouri Univ. Sci. & Technol.)

The UNM Fission Spectrometer for Individual Fission Fragment Identification from 239Pu and 235U with Correlated A, Z, E, and Fission Tagged Gamma-Ray Data

Adam Hecht, Phoenix Baldez, Mark Wetzel (Univ. New Mexico)

Transient Flux Neutron Activation Detector

William G. Culbreth (Univ. Nevada)

A Data Driven Methodology for Estimation of Background Spectrum Utilizing Paired Machine Learning Tools

Miltiadis Alamaniotis (U.T., San Antonio)

Simulation Study of Alpha-Neutron Reactions from AmBe Directional Source

Kyle M. Paaren, Hyoung K. Lee (Missouri Univ. Sci. & Technol.)

Pulsed Thermal Tomography Nondestructive Evaluation of Additively Manufactured Reactor Structural Materials

Alexander Heifetz, J. G. Sun (ANL), Dmitry Shribak (ANL, Univ. Chicago), Tiffany Liu (ANL, Univ. California, Berkeley), Thomas Elmer, Peter Kozak, Sasan Bakhtiari (ANL), Boris Khaykovich (MIT), William Cleary (Westinghouse)

TEM Analysis of Additively Manufactured Stainless Steels Prior to Neutron Irradiation

Ryan Collette, Jeffrey King, Behnam Amin-Ahmadi (Colorado School of Mines)

Neutron Irradiation Effects on Additively Manufactured Stainless Steels and Inconels: Pre-Irradiation Mechanical Property Testing

Mark Graham, Charlie Becquet, Jeffrey King (Colorado School Mines)

Neutron Irradiation Effects on Additively Manufactured Stainless Steels and Inconels: Pre-Irradiation Thermophysical Property Testing

Mark Graham, Jeffrey King (Colorado School Mines)

Determining Failure Thresholds for Coated Zircaloy Claddings in Reactivity Initiated Accidents

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

Bison Fuel Performance Studies on the Effect of Narrowing TREAT’s Pulse Width

C. Folsom, C. Davis, N. Woolstenhulme (INL)

Investigating Oklo Fuel Fission Product Retention by NAUTILUS, TEM, NanoSIMS

Evan Groopman, David Willingham, Kate Burgess (U.S. Naval Research Lab), Larry Nittler (Carnegie Inst.), Rhonda Stroud (U.S. Naval Research Lab), Alex Meshik, Olga Pravdivtseva (Washington Univ., St. Louis)

Post-Irradiation Examination Results of Miniature Fuel Specimens Irradiated in the High Flux Isotope Reactor

A. G. Le Coq, R. N. Morris, C. M. Petrie, J. R. Burns (ORNL)

Feasibility Testing of Delayed Scintillator Screens for Indirect Digital Neutron Radiography of Irradiated Nuclear Fuel

William Chuirazzi (INL, Ohio State), Aaron Craft, Nicholas Boulton (INL), Andrew Smolinski (Ohio State), Amanda Smolinski (Idaho State), Mike Ruddell, Kyrone Riley, Glen Papaioannou (Ohio State)

Long-Term Thermal Testing of Irradiated TRISO Fuel Particles from the AGR-2 Experiment

Tyler J. Gerczak, John D. Hunn, Zach Burns, Darren J. Skitt (ORNL)

Microstructural Evolution of Metallic Fuel After a Power Transient

F. G. Di Lemma, K. Wright, L. Capriotti, B. Miller, D. Murray, C. Jensen (INL)

Advanced Test Reactor I-Loop Irradiation Facility and Flux Booster Element

Keith Means (MPR), Thomas Maddock, Nicolas Woolstenhulme, Nate Oldham, Kendell Horman (INL)

Neutron Radiography and Radiation Effects Testing Using a High-Flux Electrically Driven Neutron Generator

Ross Radel, Michael Taylor, Chris Seyfert, Josh McCumber, Lucas Jacobson, Evan Sengbusch (Phoenix LLC)

Progress in Critically Assessing the NSUF Research Portfolio

Simon M. Pimblott, J. Rory Kennedy (INL)

Assessment of Additively-Manufactured Zircaloy-2 for LWR Applications

Jonna M. Partezana, William T. Cleary, Peng Xu (Westinghouse)

High Power Irradiation Testing of TRISO Particles in Miniature Fuel Specimens in HFIR

Ryan Latta, Blaise Collin, Micah Hackett (Kairos), Nicholas Brown (U.T., Knoxville), John Hunn, Christian Petrie, Tyler Gerczak, Grant Helmreich (ORNL)

X-Ray Diffraction-Computed Tomography (XRD-CT) Facility at NSLS-II for Nuclear Materials

Mehmet Topsakal, David Sprouster, Lynne Ecker (BNL)

MCNP5 Validation with a High-Reactivity Experiment in the Advanced Test Reactor Critical Facility

Joseph W. Nielsen, David W. Nigg (INL), Jeong Sik Yim (KAERI)

Plutonium Handbook—I–Panel

Robert Hanrahan (NNSA)

Plutonium Handbook—II–Panel

Robert Hanrahan (NNSA)

Fiber Optic Pressure and Temperature Sensors for Gen IV Reactor Environments

Steven Derek Rountree, Anastasia Stuckner, Matthew T. Viele Haggerty (Luna Innovations), Mohan Wang, Kevin Chen (Univ. Pittsburgh)

Optical Data Method for MARCH-Based Tests in TREAT Reactor

David Coy, Casey Cadman (Univ. Pittsburgh), Nicholas Woolstenhume, Austin Fleming (INL), Heng Ban (Univ. Pittsburgh)

The Development of an Optical Fiber Based Gamma Thermometer

Anthony Birri, Thomas E. Blue (Univ. Michigan)

High Speed Boiling Detector Based on Electrical Impedance Measurement for Advanced In-Pile Boiling Studies

C. Jensen, A. Fleming, K. Condie, J. Svoboda, E. Larsen (INL)

Transient Needle Probe Technique for In-Pile Thermal Conductivity Measurements

Austin Fleming (INL), Courtney Hollar (Boise State), Kurt Davis, Colby Jensen (INL), David Estrada (Boise State)

Sensitivity Analysis of Silicon Carbide Composite Clad Uranium Carbide Fuel for a Long-Life Gas-Cooled Fast Reactor Under Normal Operation

Hangbok Choi, John Bolin (General Atomics)

Utilization of Several Post-Irradiation Measurement Techniques to Determine Axial Growth in EBR-II Fuel

Travis Wright (Texas A&M), Douglas L. Porter (INL)

Microstructural Evolution of Neutron Irradiated T91 Steel in ATR

T. P. Davis, D. E. J. Armstrong (Oxford), P. Hosemann (U.C., Berkeley)

An Innovative Approach to Composite Moderators Containing Zirconium Hydrides

Caen Ang (U.T., Knoxville), Lance Snead, Jason Trelewicz (Stony Brook Univ.)

Mechanisms Engineering Test Loop (METL): A Liquid Sodium Component Test Facility

E. Kent, C. Grandy, D. Kultgen, M. Weathered (ANL)

A Simplified Mechanistic Approach for Modeling Thermal Conductivity of Metallic Nuclear Fuels

Tsvetoslav R. Pavlov (INL)

Direct, Uncorrected Analysis of Mixed Oxide Particle by NAUTILUS

David Willingham, Evan Groopman (U.S. Naval Research Lab), Laure Sangely (IAEA)

Mid-Irradiation Experiment Examinations of Monolithic U-10Mo Fuel MP-1 Irradiation Tests at the Advanced Test Reactor

Margaret A. Marshall, James Smith, Clark Scott, David Cottle, Casey Jesse (INL)

Development of the Irradiation Plan for the ET-2 and ET-3 Tests to Support Qualification of U-10Mo Fuel for use in the Advanced Test Reactor

Douglas E. Hardtmayer, Kyle G. Metzroth (MPR Assoc.), Matthew Johnson, Eric Woolstenhulme (INL)

Analysis of Matrix Graphite Degradation Under Varied Oxidizing Atmospheres

Katherine Montoya, Brian A. Brigham (U.T., San Antonio), Tyler J. Gerczak (ORNL), Elizabeth Sooby Wood (U.T., San Antonio)

Fission Product Measurement and Off-Gas Scrubbing for Molten Salt Reactors

J. McFarlane, G. Del Cul, D. B. Ezell, K. Myhre (ORNL), S. A. Bryan, H. M. Felmy, A. Lines, B. J. Riley (PNNL)

Capturing Chemical Dynamics at the Buried Electrode-Electrolyte Interface by In Situ Imaging Mass Spectrometry

Xiao-Ying Yu, Edgar Buck (PNNL)

Characterization of Nuclear Graphite for Molten Salt Reactors (MSR)

Nidia C Gallego, Cristian Contescu, Tim Burchell, James Keiser, Stephen Raiman (ORNL), Karol Putyera (Eurofins), Lou Qualls (ORNL)

Study on Irradiation Hardening of RPV Steel Based on Modified Crystal Plastic Finite Element Model

Xiaotong Wang (Reactor Sys. Des. Technol. Lab), Weihua Yao (Nuclear Power Inst. China), Ying Luo, Yuanyuan Dong (Reactor Sys. Des. Technol. Lab)

Evaluation Methods of Fatigue in Nuclear Power Design

Donghui Wang, Qingna Zeng (Nuclear Power Inst. China)

Alkali-Silica Reaction Detection Utilizing Linear and Nonlinear Resonance Frequency Shift Techniques

Clayton Malone, Hongbin Sun, Jiong Hu, Jinying Zhu (Univ. Nebraska)

Measuring Heterogeneity of SiCf /SiC Tubular Composites

James Nance, Hemanth T. Nagaraju, Ghatu Subhash, Bhavani Sankar, Raphael Haftka (Univ. Florida)

The Effect of Calculating the Micromechanical Stresses in Braided Composite Tubes by a Flat RVE

Hemanth T. Nagaraju, James R. Nance, Bhavani Sankar, Ghatu Subhash, Raphael Haftka (Univ. Florida)

SiGATM Bowing Due to Thermally-Dependent Irradiation-Induced Swelling

J. L. Kosmatka, J. Stone, G. M. Jacobsen, J. Gazza, C. P. Deck (General Atomics)

Modeling of SiC Cladding Bowing Behavior with Consideration of Spacer Grids

Wei Li (MIT, China), Koroush Shirvan (MIT)

Fabrication of Fully Ceramic Microencapsulated Compacts for Miniature Fuel Specimen Irradiation

Rachel L. Seibert, Joseph R. Burns, James O. Kiggans, Kurt A. Terrani (ORNL)

Aging Effect of Chromium Coated Zircaloy-4 Accident Tolerant Fuel Cladding Material

Rajnikant Umretiya, Santiago Vargas, Robert Uhorchuk, Carlos E. Castano, Jessika Rojas (VCU)

DFT + U Study of Electronic and Lattice Thermal Conductivity of the Hypostoichiometric UO2

T. P. Kaloni , N. Onder (CNL), J. Pencer (CNL, McMaster Univ.), E. Torres (CNL)

Current Issues in Computational Methods–Roundtable

Robert Grove (ORNL)

Best Practices of Nuclear Software Quality Assurance–Panel

Travis Trahan (LANL)

Preliminary Results for Particle Tracking on Weight Window Isosurface Geometries for Monte Carlo Variance Reduction

Kalin R. Kiesling, Paul P. H. Wilson (U.W., Madison)

Thermal Radiation Transport in Random Media with Temperature Dependent Opacities

Corey M. Skinner, Anil K. Prinja (Univ. New Mexico)

An Arbitrary Lagrangian Eulerian Solver for Shock Imploding Fissile Materials

Eric Cervi, Antonio Cammi (Politecnico di Milano)

A Coupled Neutronics Shock Physics Solver: Implementation of an SN Neutron Transport Module

Eric Cervi, Antonio Cammi (Politecnico di Milano)

Optimization of the Rattlesnake Code with Array Variables/Kernels

Yaqi Wang, Derek Gaston, Alexander Lindsay, Vincent Laboure (INL)

Spherical Functional Expansions in MOOSE

Brittany Grayson, Leslie Kerby (Idaho State)

Optimization of Axial interpolation for the FM Control Rods Algorithm in RAPID

Valerio Mascolino, Alireza Haghighat (Virginia Tech), Luka Snoj (Jožef Stefan Inst.)

Investigation of Fission Matrix Homogenization and Iterative Convergence in RAPID

Donghao He, William J. Walters (Penn State)

Theoretical Convergence Study of lpCMFD for Fixed Source Neutron Transport Problems in 2D Cartesian Geometry

Yimeng Chan, Sicong Xiao (National Univ. Singapore)

A Discontinuous Finite-Element Formulation of the Gray Radiative Heat Transfer P1 Equations Using a Moving Mesh Partial Differential Equation

Hans Hammer, HyeongKae Park, Luis Chacón, William Taitano (LANL)

Axially Quadratic Discontinuous Finite Elements for Neutron Transport Reactor Simulations

Robert F. Turner, Jean C. Ragusa (Texas A&M)

A Modified Step Characteristic Method for Solving the SN Transport Equation

Dean Wang (Ohio State), Zeyun Wu (VCU)

A High-Order / Low-Order (HOLO) Algorithm with Low-Rank Evolution for Time-Dependent Transport Calculations

Zhuogang Peng, Ryan McClarren (Notre Dame)

Analytic Discrete-Ordinates Solution for Time-Dependent Transport in Semi-Infinite Media

Jeffery D. Densmore, Gabriel Kooreman (Naval Nuclear Lab.)

Monoenergetic Time Dependent Diffusion in 1D Heterogeneous Media

B. Ganapol (Univ. Arizona), M. DeHart, F. Gleicher, S. Schunert, R. Martineau (INL)

Extending Wang’s 1D Sn Analytic Solution to Heterogeneous Problems with No Iteration on Interfacial Fluxes

Zeyun Wu (VCU)

Accelerating Radiation SN Transport Solves using Artificial Neural Networks

Mauricio E. Tano, Jean C. Ragusa (Texas A&M)

Machine Learning Accident Classification Using Nuclear Reactor Data

Pedro Mena, Leslie Kerby (Idaho State)

Acceleration of the Flattened Power Method with Dynamic Mode Decomposition

Leidong Xu, Richard L. Reed, Jeremy A. Roberts (Kansas State)

Data-Driven Grey Reduced-Order Model for Thermal Radiative Transfer Problems Based on Low-Order Quasidiffusion Equations and Proper Orthogonal Decomposition

Joseph Coale, Dmitriy Anistratov (NCSU)

Reduced Order Model with Constrained Optimization for Navier-Stokes Equations

Ping-Hsuan Tsai, Kento Kaneko, Paul F. Fischer (Univ. Illinois)

Model-Order Reduction of Buoyancy-Driven Heat-Transfer

Kento Kaneko, Ping-Hsuan Tsai, Paul Fischer (Univ. Illinois)

Bengal: A Multigroup Cross Section Processing Code for Large-Scale Calculations

Steven J. Douglass, Nathan A. Gibson (Naval Nuclear Lab.)

A Graph Approach for Radioactive Decay Calculation

Tae-Sic Yoo (INL)

Sensor Error Estimation for Reactor Coolant System with Generalization Error Equations

Nageswara S. V. Rao, Pradeep Ramuhalli, Christopher Greulich, Sacit M. Cetiner (ORNL)

Impact of the Choice of Probability Distribution Laws for Nuclear Data on Depleted Fuel Related Quantities

Sebastien Lahaye (CEA), Keisuke Honta (Hokkaido Univ.), Pierre Bellier, Aime Tsilanizara (CEA)

International Criticality Benchmark Comparison for Nuclear Data Validation

Isabelle Duhamel (IRSN), J. L. Alwin, F. B. Brown, M. E. Rising, K. Y. Spencer (LANL), D. Heinrichs3, S. Kim (LLNL), B. J. Marshall, E. M. Saylor (ORNL)

Recent SCALE Activities Within the Nuclear Criticality Safety Program

W. A. Wieselquist (ORNL)

Automated Acceleration and Convergence Testing for Monte Carlo Nuclear Criticality Safety Calculations

Forrest B. Brown (LANL)

Evaluation and Validation of 181Ta Unresolved Resonance Region Cross Section

Jesse M. Brown, Amanda Youmans (RPI), Michael J. Rapp (Naval Nuclear Lab.), Ezekiel Blain (RPI), Devin P. Barry (Naval Nuclear Lab.), Yaron Danon (RPI)

Time Series Neutron Data from Subcritical Experiments for Validation of Radiation Transport Codes

Anthony J. Nelson, William Zywiec, Soon S. Kim (LLNL), Wilfried Monange (IRSN), David Heinrichs (LLNL)

Sandia BUCCX Titanium and Aluminum Sleeve Experiments

David E. Ames, Gary A. Harms, John T. Ford, Rafe D. Campbell (Sandia)

Impacts to Criticality Safety from Recent Revisions to DOE Standards–Panel

Andrew Prichard (PNNL), John Miller (SNL), Kevin Kimball (CNS, Ret.)

Implications of NCS Analysis Process Drift–Panel

Christopher Haught (Consolidated Nuclear Security), John Miller (SNL), Andrew Prichard (PNNL)

The 2019 Edition of the ICSBEP Handbook

John D. Bess (INL), Tatiana Ivanova, Ian Hill (OECD), Lori Scott (INL)

Redux Analysis of D2O Reflected Plutonium Foils at Low Temperature

William J. Zywiec, Anthony J. Nelson (LLNL)

Thermal Neutron Scattering Cross Sections of U-10Mo

Andrea A. Saltos, Nickie J. Peters , Karl D. Hammond (Univ. Missouri)

The Effect of Size and Shape in Heterogeneous Systems of Small Uranium Pieces

Kristina Yancey Spencer (LANL)

Seventy-Five Years of Nuclear Criticality Safety Documents—A Bibliography

Brian L. Koponen, David P. Heinrichs (LLNL)

Verification of the 239Pu(NO3)4 Solution Fissile Concentration Subcritical Limit in ANSI/ANS-8.1-2014

Douglas G. Bowen (ORNL), Nicholas W. Brown (Nuclear Fuel Services)

Update on Benchmark Analysis of Component Critical Configurations of KRUSTY

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

Analytic One-Group S2 Slab Problem with Isotropic Scattering and Fission Applied to Leakage and Neutron Multiplicity Sensitivity

Jeffrey A. Favorite (LANL)

Differences in the Use of Nuclide ? Vectors Demonstrated with an Analytic k? Problem

Jeffrey A. Favorite (LANL)

K-Infinite Comparison of Uranium Compounds at 5 wt.% U235

Lon E. Paulson (GE Hitachi)

Effect of keff Varying Reflection on the Estimated Minimum Critical Mass of Moderated 235U

E. M. Saylor (ORNL)

Proposed Plutonium-Nickel Critical Experiment

T. Cutler, N. Thompson, A. McSpaden, J. Hutchinson (LANL)

Sensitivity/Uncertainty Comparison Study: Oak Ridge National Laboratory Results

E. M. Saylor, W. J. Marshall (ORNL)

Bias Between ENDF/B-VIII and ENDF/B-VII.1 for LEU Pin Array Systems

W. J. Marshall (ORNL)

A Graded Approach to the Selection of Minimum Subcritical Margin

Joseph Christensen (SHINE Medical Technol.)

Subcriticality Measurement Using Feynman-? Analysis with a Fully Random Sampling and Second-Order Filtering Technique for AGN-201K

Sungho Moon, Jong Hoon Kim, Myung Hyun Kim, Ser Gi Hong (Kyung Hee Univ.)

Determination of Bounding Axial Burnup Profiles for Criticality Analysis with Burnup Credit for Spent Fuels Discharged from OPR-1000

Dong Jin Kim, Kyu Jung Choi, Ser Gi Hong (Kyung Hee Univ.)

Introduction to NCSD Mentor Match and Membership Challenge Debrief–Panel

Hannah Morbach (BWXT), Jennifer Alwin (LANL), John Miller (SNL), MacKenzie Gorham (DOE)

Data-Driven Safety Margin Management Using Reduced Order Modeling

Jun Liao, Clarence L. Worrell, James P. Spring (Westinghouse)

Development of Efficient Data Sampling Method to Construct Surrogate Model of Severe Accident Analysis Code for SBO Aiming Probabilistic Safety Margin Analysis

Masaki Matsushita, Tomohiro Endo, Akio Yamamoto (Nagoya Univ.)

Easily-Adapted Quantification Tools for Operating Events’ Significance

Chang-Ju Lee, Dongju Jang (KINS)

Feedwater Pipe Break-Induced Hydraulic Loads on Nuclear Steam Generator Tubes

Jong Chull Jo, Jae Jun Jeong, Byong-Jo Yun (Pusan Natinoal Univ.)

Considerations for Early-Stage Safety Assessments for Advanced Reactor Designs

Brandon Chisholm, Steve Krahn, Megan Harkema (Vanderebilt), Andrew Sowder (EPRI), Carole Leach (Vanderebilt)

Integrated Probabilistic Risk Assessment (I-PRA) Importance Ranking for Fire PRA of Nuclear Power Plants

Ha Bui, Tatsuya Sakurahara, Seyed Reihani, John Biersdorf, Zahra Mohaghegh (Univ. Illinois)

Development of Severe Accident Mitigation Technology and Analysis Method for Small Integral Reactor

Rae-Joon Park, Donggun Son, Hyung Seok Kang, Sang-Mo An (KAERI)

Future Directions for the Defense Nuclear Facilities Safety Board–Panel

Charles Martin (Longenecker & Associates)

Current Applications of Dynamic PRA–Panel

Matthew Denman (Kairos)

Realizing the Benefits of Risk-Informed and Performance-Based Approaches–Panel

Robert Youngblood (INL)

Round Table on Non-Reactor Nuclear Facility Consensus Standards

Charles Martin (Longenecker & Associates)

Discussion on Challenges for New Regulatory Oversight Program for Nuclear Facilities in Japan

Hiroko Kondo (Univ. Tokyo)

Development of Methodology for Spent Fuel Pool Risk Assessment in Korea

Kyungmin Kang, Hyowon Kim, Kuyoung Jung (KINS)

Off-Site Consequence Analysis for Multi-Unit Considering Inter-Unit Dependency

YongJin Lee, Dohyoung Kim, Kuyoung Jung (KINS)

Identification of Multi-Unit Initiating Events Using Operating Experience in Korea

Kihan Jeon, Seungwoo Lee, Ar Ryum Kim, Hyowon Kim, Dongju Jang, Dohyoung Kim (KINS)

Dwight D. Eisenhower Award Special Session—I

James Behrens (U.S. Navy)

Dwight D. Eisenhower Award Special Session—II

James Behrens (U.S. Navy), Kelsey Amundson

SMR Safeguards–Panel

Chloe Verschuren (LANL)

Table Top Exercise–Panel

Kelsey Amundson

Investigation of Application Specific keff Sensitivities to Existing and New Subcritical and Critical Experiments

T. Smith, J. Alwin, R. Bahran, T. Grove, J. Hutchinson, R. Little, I. Michaud, A. McSpaden, B. Myers, M. Rising, N. Thompson, D. Hayes (LANL)

Designing Critical Experiments Using Gaussian Process Optimization

Isaac Michaud, Noah Kleedtke, Jesson Hutchinson, Travis Smith, Robert Little, Travis Grove, Michael Rising (LANL)

Adding (?,n) Emission to an Existing Subcritical Benchmark Statistical Uncertainty Method

J. Hutchinson, J. Arthur, T. Cutler, T. Grove, M. Nelson (LANL)

Optimization of Binning Parameters in the Feynman Variance-to-Mean Method for Delayed Neutron Reinterrogation

A.Harvis, J. Determan, J. Hutchinson, W. Myers (LANL)

Preliminary Designs for Criticality Safety Benchmarks—Iron/Steel/Chromium Series

Nicholas Thompson, Jesson Hutchinson, Theresa Cutler, William Myers, David Hayes (LANL)

Prompt Neutron Decay Constant Measurements on a Copper Reflected Intermediate Enrichment Uranium System with Lead Intersitial

George McKenzie, Travis Grove, Rene Sanchez (LANL)

Jupiter: A Proposed Benchmark for Lead Void Worth with Plutonium

Alex McSpaden, Joetta Goda, Theresa Cutler, George McKenzie, Jesson Hutchinson, Nicholas Thompson (LANL)

Two-Exponential Rossi-Alpha Analysis of Copper- and Polyethylene-Reflected Plutonium

M. Y. Hua (Univ. Michigan, LANL), C. A. Bravo (Univ. Michigan), J. D. Hutchinson, G. E. McKenzie (LANL), S. A. Pozzi (Univ. Michigan)

Investigation of Nuclear Safeguards Attributes Through Neutronics Simulation of Pebble Bed Reactor Core

Dany Mulyana, Sunil S. Chirayath

Arms Control and Treaty Verification–Panel

Alicia Swift (Y-12)

Gamma Source Imaging Using Non-Negative Least Squares

Nuraslinda Anuar (Texas A&M, Univ. Tenaga Nasional), Craig M. Marianno (Texas A&M)

Validating a Protocol for Low Level EPR Dosimetry of Sugar

Fatma Abdelrahman, Robert B. Hayes (NCSU)

Determination of Characteristics in Post Detonation Debris Collection Scenarios Using Modern Urban Materials

Justin Phelps, James E. Baciak (Univ. Florida)

University of California's Experience with Gamma-Irradiators, X-Irradiators, and Radiobiology

Keisuke S. Iwamoto (UCLA), Carolyn MacKenzie (U.C., Berkeley)

Alternative X-Ray Sources as Substitutes for Radioactive Isotopes in Irradiation Applications

Mark Eaton, Ronald Hellmer, Zhe Su, Shuo Cheng (Stellarray)

Transitioning from Cobalt-60 to X-Ray or E-Beam for Medical Sterilization: Filling Data and Education Gaps

Leonard S. Fifield, Matt Pharr (PNNL), David A. Staack (Texas A&M), Mark K. Murphy (PNNL), Min Huang, Md Kamrul Hasan (Texas A&M)

Effect of Thermal Energy Storage Integration on Overall Nuclear Power Plant Efficiency

Mohamed Ali, Ahmed K. Alkaabi, Saeed A. Alameri, Mohammad Alrwashdeh (Khalifa Univ.)

Nuclear Heat Storage & Recovery System Design for the APR1400

Robert M. Field, Andrew Tetteh Ashong, Kafilat Funmilola Amuda (KEPCO)

Thermodynamic Evaluation of Thermal Energy Storage Applied to the APR1400

Anna Kluba, Robert M. Field (KEPCO)

Heat Storage for Gen IV Reactors for Variable Electricity from Base-load Reactors: Workshop Summary

Charles Forsberg (MIT), Hans D. Gougar, Piyush Sabharwall (INL)

Theoretical Background and Case Study for the Exergo-Economic Optimization of a Large-scale Electricity Storage System Using Supercritical Carbon Dioxide

Baptiste Py (Ecole Nationale Supérieure des Mines, KAIST), Yong Hoon Jeong (KAIST)

Assessment of Small Modular Reactors (SMRs) for Load-Following Capabilities

Y. Ismail, B. P. Bromley (CNL)

Phase Change Material Candidates for High-Temperature Nuclear Reactor Heat Storage

W. Neal Mann, Sheldon Landsberger, Michael E. Webber (Univ. Texas, Austin)

Transient Effects and Material Challenges in Developing Chemical/Absorption Heat Pumps for Nuclear Energy Thermal Storage and Upgrade

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

Performance of an Experimental Ca(OH)2/CaO Chemical Heat Pump Under Repeated Thermal Cycling

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

Thermal Energy Storage Selection for Near Term Nuclear Integration

Daniel Mikkelson (NCSU), Konor Frick (INL), J. Michael Doster (NCSU), Shannon Bragg-Sitton (INL), Elizabeth Worsham (NCSU)

Preliminary Feasibility Study on the Conversion of the High Temperature Test Facility (HTTF) into a Firebrick Thermal Energy Storage System

J. Johnson, B. Leitherer, W. Williams, D. Zimmerly, B. Woods (Oregon State)

New Construction Around the World–Panel

Edward Quinn (Technology Resources)

MicroReactors–Panel

Piyush Sabharwall (INL), Zachary Jankovsky (SNL)

Preliminary Design of Cartridge Loops in Support of the Fuel Testing Campaign of the VTR

Silvino A. Balderrama Prieto, Piyush Sabharwall (INL), Mitchell T. Farmer (ANL)

Numerical Investigation of Fluid Flow in a Square Channel—Versatile Test Reactor Program

Byung-Hee Choi, Daniel Orea, Thien Nguyen, N. K. Anand,1 Yassin Hassan (Texas A&M), Piyush Sabharwall (INL)

Experimental Investigation of Surrogate Particle Transport in a Turbulent Channel Flow: Versatile Test Reactor Program

D. Orea, R. Chavez, D. T. Nguyen, R. Vaghetto, N. K. Anand, Y. A. Hassan (Texas A&M), Piyush Sabharwall (INL)

Flow Test Plan to Support the Development of Cartridge Loops in the Versatile Test Reactor

Joel McDuffee, David Felde (ORNL), Kevan Weaver (INL), Mitch Farmer (ANL), Piyush Sabharwall (INL), Richard Howard, Padhraic Mulligan (ONRL)

Assessment of Lead Loop Design and Demonstration of a Generic Closed Loop Modeling for System Analysis

Seung Jun Kim, Keith Woloshun, Cetin Unal, Russel Johns

Versatile Test Reactor—II–Panel

Piyush Sabharwall (INL)

Delivering a New Reactor Technology—What Role Does the Nuclear Regulator Play in the Decision to Deploy a New Reactor–Panel

John Brister (AECOM)

The Role of Innovation in Nuclear Development–Panel

Fiona Rayment (National Nuclear Laboratory)

Efficiency Analysis of Hybrid Rankine Cycle for HTR-NHR Combined NPP

Li Bowen, Dong Zhe, Liu Miao (Tsinghua Univ.)

Sodium Cooled Reactor Containment Building Footprint Optimization

Michael Smith (Univ. North Carolina), John McEntire, Paul Murray (Orano), Thomas Koch (Univ. North Carolina)

High Cost of Nuclear Power Plants in the U.S. and Systematic Approach to the Issue

Efe G. Kurt, Mark DeHart, Phillip Finck (INL)

Dynamic Matrix Control for Thermal Power of Multi-MHTGR

Di Jiang, Zhe Dong (Tsinghua Univ.)

Novel Design Integration for Advanced Nuclear Heat-Pipe Systems

Cole Mueller, Pavel Tsvetkov (Texas A&M)

Integrating LWR with High Renewable Generation–Stochastic Control Based on Langevin Model

M. Ross, A. Gairola, H. Bindra (Kansas State)

Evaluating the MSRE Sampler-Enricher: A Fresh Perspective

Megan Harkema, Steven Krahn, Paul Marotta (Vanderbilt)

Establishing the Requirements for Japan's Future Nuclear Energy Systems

W. Robb Stewart, Jacopo Buongiorno, Koroush Shirvan, Emilio Baglietto, Charles Forsberg, Michael Driscoll (MIT)

Assessing Risk Recognition and Decision-Making (RRDM)

Michael Peckham, Dennis Hansen (Marathon Consulting)

ANS Position Statement 41 on the Effect of Low-Levels of Radiation–Panel

Shaheen Azim Dewji (Texas A&M)

The Double Threshold of Low Dose Radiation

Alan Waltar (Atomic Talk), Ludwig Feinendegen (Heinrich-Heine Univ.)

Towards Portable Muon Tomography System for Non-Destructive Detection of Nuclear Materials

O. Kamaev, E. T. Rand, K. Hartling, A. Erlandson (CNL)

Improvement of the Self-Sealing Simulation Code Including the Solid Layer

Yonadan Choi, Dong Hoon Kam, Yong Hoon Jeong (KAIST)

Initial Development of Radiation Protection MCNP Modeling in Neutron Activation Analysis (NAA) Laboratories

Jose Rafael Parga (LANL, U.T., Austin), Sheldon Landsberger, Kevin. Clarno (U.T., Austin)

Monte Carlo Analysis of Optimally Selected Dose Points for the Additive Dose Method for Retrospective Dosimetry

Ryan P. O'Mara, Robert B. Hayes (NCSU)

Geant4 Simulation for Rotating Pencil Beam Far-Side MV Backscatter Imaging

Shuang Cui, Jyothier K. Nimmagadda, James E. Baciak (Univ. Florida)

l3d2vtk: An MCNPTools Utility to Enable LNK3DNT File Visualization & Post-Processing

Joel A. Kulesza, Jennifer L. Alwin, Jesson D. Hutchinson, Erik F. Shores, Robert C. Little (LANL)

Analysis of Dose Rates Around a Silo-Type LILW Repository Using ADVANTG

Luka Snoj, Domen Kotnik, Bor Kos (Jožef Stefan Inst., Univ. Ljubljana)

Application of Global Weight Window Generator Based on Particle Density Uniformity in Deep-Penetration Shielding Calculation

Peng He, Bin Wu, Lijuan Hao, Guangyao Sun (Inst. of Nuclear Safety Technology)

An Overview of the Modernized Generalized Spallation Model

Chase Juneau, Clell Solomon, Leslie Kerby (LANL)

Analysis of Operational History Effects on the Shielding Calculation of the KN-12 Cask Using Monaco/MAVRIC

Ye Seul Cho, Ser Gi Hong (Kyung Hee Univ.)

Critical Benchmark Verification of cosSHIELD Particle Transport Code

Yeshuai Sun (SPIC, National Energy Key Lab.), Bin Zhang (National Energy Key Lab., North China Electric Power Univ.), Wen Song, Shuo Li, Hui Yu, Yixue Chen (SPIC, National Energy Key Lab.)

Calculating the Differential Physics of Neutron Transport in Nitrogen Based on Integral Experiments from the Livermore Pulsed Sphere Program

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

Experimental Benchmark for the DRF Methodology Using VENUS-3 Problem

Meng-Jen Wang, Alireza Haghighat (VCU)

Attila and MCNP6.2 Validation with the JASPER-IHX Benchmark for Sodium-Cooled Fast Reactor Shielding Applications

Nicholas H. Whitman (Oregon State), Jacob S. Hader (TerraPower)

Fluence on the Surface of an Absorbing Sphere

Amir A. Bahadori, Michael P. Pfeifer, J. Kenneth Shultis (Kansas State)

Monte Carlo Source Descriptions for Unenriched Uranium Fuel and a PuBe Neutron Source

Cliff Ghiglieri, Jeffrey King (Colorado School Mines)

Comparison of MCNP6.1-Computed Dosimetric Quantities Using Spherical and Full-Body Computational Phantoms

S. R. McHale, E. R. Walker (U.S. Naval Academy)

Deconvolution of Uncertainty Components in Transuranic Air Sample Assay Measurements

S. Joseph Cope, Robert B. Hayes (NCSU)

Comparison of Atmospheric Dispersion and Deposition Factors Between Different Approaches

Seung-Hee Lee (KEPCO), Won-Tae Hwang (KAERI), Chang-Lak Kim (KEPCO)

Considerations for Angle and Energy Dependent Dose Response Function Utilization for Neutron Transport in Air

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

Atmospheric Gamma-Ray Transport from a Radioactive Cloud to a Low Earth Orbit Satellite Using MCNP

Jacob W. Inman (Georgia Tech), Brandon A. Wilson, Vincent J. Jodoin (ORNL)

C5G7 MOX Benchmark Calculation with the High-Performance Pin-by-Pin Two-Step Calculation Procedure

Joo Il Yoon (KEPCO), Hyun Sik Hong (Seoul National Univ.)

Reduction of Macroscopic and Microscopic Cross Section Table Size for Heterogeneous Core Calculation Using Dimensionality Reduction

Masato Yamamoto, Tomohiro Endo, Akio Yamamoto (Nagoya Univ.)

MCNP and SERPENT Monte Carlo Modeling of a Water Level Transient Experiment

A. Talamo, Y. Cao, Y. Gohar (ANL), S. Sikorin, S. Mandzik, S. Polazau, T. Hryharovich (Joint Inst. For Power and Nuclear Research), V. Valtavirta, J. Leppänen (VTT)

Resonance Calculation Using Energy Spectral Expansion Based on Reduced Order Model: Application to Heterogeneous Geometry

Akio Yamamoto, Ryoichi Kondo, Tomohiro Endo (Nagoya Univ.), Satoshi Takeda (Osaka Univ.), Hiroki Koike, Kazuya Yamaji, Daisuke Sato (Mitsubishi)

The Roles of Transport Partial Current Information in Two-Level p-CMFD Acceleration in the Whole-Core Transport Calculation

Nam Zin Cho (KAIST)

A Preliminary Application of the GPS Correction to Pin-by-Pin 2-Step PWR Depletion

Hwanyeal Yu (KAIST), Hae Sun Jeong (KAERI), Yonghee Kim (KAIST)

Polaris/PARCS Prediction of Measured Data for TMI Unit 1 Cycles 1 and 2

True Miller (Purdue), Andrew Ward (Univ. Michigan), Yunlin Xu (Purdue)

Improved Discontinuity Factor Modeling for the In-Situ APEC Leakage Correction in Nodal Analysis

Seongdong Jang, Yonghee Kim (KAIST)

Molten Salt Reactor Neutronic and Fuel Cycle Sensitivity and Uncertainty Analysis

J. W. Bae, B. R. Betzler, A. Worrall (ORNL)

Steve Bowman Memorial Session: Evolution of Scale–Panel

William Wieselquist (ORNL)

Sensitivity and Uncertainty Analysis of the Advanced Burner Reactor Core Using NEAMS Workbench

Kaiyue Zeng (NCSU), Nicolas E. Stauff (ANL),Jason Hou (NCSU)

Development of Neural Thermal Scattering (NeTS) Modules for Reactor Physics Applications

C. A. Manring, A. I. Hawari (NCSU)

Development of Processing Tool to Generate Covariance of Multigroup Thermal Scattering Matrix

Hansol Park, Aaron G. Tumulak (Univ. Michigan), Vladimir Sobes (ORNL), Won Sik Yang, Brian C. Kiedrowski (Univ. Michigan)

Hydrogen Vacancy Effect on Yttrium Hydride (YH1.97) Thermal Neutron Scattering Law

Vedant Mehta (LANL, Georgia Tech.), Michael W D. Cooper (LANL), Dan Kotlyar (Georgia Tech.)

ENDF/B-VIII.0 Augmented Covariance Data: The First Iteration

Vladimir Sobes, William J. Marshall, Doro Wiarda, Friederike Bostelmann, Andrew Holcomb, Bradley T. Rearden (ORNL)

Impact of the ENDF/B-VIII.0 Library on Advanced Reactor Simulations

Friederike Bostelmann, Andrew M. Holcomb, William J. Marshall, Vladimir Sobes, Bradley T. Rearden (ORNL)

Sensitivity Analysis and Uncertainty Quantification of FFTF Cycle 8C Using the NEAMS Workbench

I. T. Usman (ANL, Univ. Witwatersrand), P. Lartaud, N. E. Stauff (ANL)

Progress on the Development of Thermal Scattering Covariance Formats and Processing Tools

Aaron G. Tumulak, Hansol Park (Univ. Michigan), Vladimir Sobes (ORNL), Won Sik Yang, Brian C. Kiedrowski (Univ. Michigan)

Safety Design Strategy for the Versatile Test Reactor

Douglas M. Gerstner, Jason Andrus (INL), David Grabaskas, Matthew Bucknor (ANL)

Shutdown Worth Requirements for the Versatile Test Reactor

Florent Heidet (ANL)

Approach to Hot Channel Factors for the Versatile Test Reactor Design

Aurelien Bergeron, Earl Feldman, Florent Heidet (ANL)

Steady-State Fuel Performance Analysis for the Versatile Test Reactor with LIFE-METAL

Aaron Oaks, Walid Mohamed, Abdellatif Yacout, Florent Heidet (ANL)

Detailed Isotopic Fuel Composition for the Versatile Test Reactor

Alisha Kasam-Griffith, Florent Heidet (ANL)

Application of the Licensing Modernization Project Approach to the Authorization of the Versatile Test Reactor

David Grabaskas (ANL), Jason Andrus (INL), Dennis Henneke (GE-Hitachi), Matthew Bucknor (ANL), Jonathan Li (GE-Hitachi), Doug Gerstner (INL), Matthew Warner (GE-Hitachi), Thomas Fanning (ANL)

Sodium Fire Progression Computational Tools for Performing Hazards Analysis of the Versatile Test Reactor

Matthew Bucknor, James Sienicki, Anton Moisseytsev (ANL)

Calculation of Neutron Damage to Sodium Coolant Inlet Plenum

Samuel E. Bays (INL), Tingzhou Fei (ANL)

Analysis of Control Rod Worth and B-10(n,?) Measurements in ZPPR-15

Gerardo Aliberti, Michael A. Smith, Richard M. Lell, Florent Heidet (ANL)

In-Situ Mechanical and Corrosion Testing for Versatile Test Reactor Application

Guillaume Mignot, Samuel Briggs, Camila Toledo Torres, George Young, Andrew Brittan, Lucas Teeter (Oregon State), Adam Wojcik (Univ. College London), Matthew Waitt (Matelect), Julie D. Tucker (Oregon State)

Design and Modeling of a Liquid-Fuel Salt Experiment for the Versatile Test Reactor

Alexander J. Huning, M. Scott Greenwood, Joel McDuffee, Kenneth Thoms (ORNL)

Establishment of an Out-of-Pile Lead Loop Facility to Support Lead Cooled Fast Reactor Design

Osman Anderoglu, Cemal Cakez, Shuprio Ghosh, Brian Romero, Khaled Talaat, Sang Lee (Univ. New Mexico), Youho Lee (Seoul National Univ.), Keith Woloshun, Seung Jun Kim, Stuart Maloy, Cetin Unal (LANL), Michael Ickes, Paolo Ferroni (Westinghouse)

Vehicle Concept for Irradiating Molten Salts in the Versatile Test Reactor

Justin W. Thomas, Todd Lockwood, Julie Jordan, Daniel Eichel, James Vollmer (TerraPower)

Analysis of the VTR In-Core Environment with the “Rabbit” Delivery System Enabling Encapsulated Irradiations

Jonathan B. Scherr, Pavel V. Tsvetkov, Jason Hearne, Sean McDeavitt (Texas A&M), David Wootan (PNNL)

Fiber Optic Sensor for Corrosion Monitoring in Molten Salt Irradiation Experiments

Christian M. Petrie (ORNL)

Modeling the IFR-1 Metal Fuel Experiment in BISON Through the NEAMS Workbench

Kaylee M. Cunningham, Jeffrey J. Powers, Robert A. Lefebvre (ORNL)

The Impact of Xenon-135 on Load Following Transatomic Power Molten Salt Reactor

Andrei Rykhlevskii, Daniel O’Grady, Tomasz Kozlowski, Kathryn Huff (Univ. Illinois)

Fabrication of Two-Phase Composite Moderators as Potential Lifetime Reactor Components

Lance Snead (Stony Brook Univ.), Nicholas Brown (U.T., Knoxville), Jason Trelewicz (Stony Brook Univ.), Caen Ang, Bin Cheng (U.T., Knoxville), Xunxiang Hu (ORNL), David Sprouster (Stony Brook Univ.)

Preliminary Reactor Physics Analysis of Alternative Moderators for Modular High Temperature Gas-Cooled Reactors

Edward M. Duchnowski, Nicholas R. Brown (U.T., Knoxville), Lance Snead, Jason Trelewicz (Stony Brook Univ.)

Application of Depletion Perturbation Theory for Sensitivity Analysis in the High Flux Isotope Reactor

Keith C. Bledsoe, Germina Ilas, Susan L. Hogle (ORNL)

Development of Perturbed MPACT Multigroup Libraries and the Perturbation Methodology for Subgroup Data

Kang Seog Kim, Matthew A. Jessee (ORNL)

Sensitivity Coefficient Calculations Using Contribution Theory

Christopher M. Perfetti (Univ. New Mexico)

Uncertainty Analysis of Pressurized Water Reactor Core Cycle Depletion Calculation

Kaiyue Zeng, Jason Hou, Kostadin N. Ivanov (NCSU)

A Novel Temperature Sensitivity Calculation Methodology for the Serpent Monte Carlo Code

Ville Valtavirta (VTT), Manuele Aufiero (Milano Multiphysics), Jaakko Leppänen (VTT)

Contributions of Mark Williams to OECD/NEA LWR-UAM Multi-Scale Reactor Physics Framework

Maria Avramova, Jaoson Hou, Kostadin Ivanov (NCSU)

Some Innovations of Dr. Mark Williams for the Practical Application of Sensitivity and Uncertainty Analysis to Reactor Analysis and Criticality Safety

B. T. Rearden (ORNL)

Quantifying SCALE/TRITON Code Discrepancy Using Spent Fuel Assay Data from SFCOMPO-2.0

Dean Reid Price, Tomasz Kozlowski (Univ. Illinois)

Uncertainty Analysis of UAM-LWR Benchmark with MCS

Yunki Jo, Woonghee Lee, Chidong Kong, Deokjung Lee (UNIST)

Monte Carlo Uncertainty Quantification in UF6 Cylinder Neutron Emissions

Ryan P. O’Mara (NCSU), Will Wieselquist, Cihangir Celik (ORNL)

Dr. Mark Williams' Three Contributions to Nuclear Data Covariance

Dorothea Wiarda, Marco Pigni, Vladimir Sobes, Bradley T. Rearden (ORNL)

“Hands On” Core Design–Panel

Amanda Lang (Duke)

Investigating Increased Volumetric Capacity BUSTER Test Vehicle Variants for TREAT

John D. Bess, Nicolas E. Woolstenhulme, Connie M. Hill (INL)

Hot-Channel and Burnup Analysis for Potential High-Power Configuration of Missouri S&T Reactor

Thaqal Alhuzaymi (King Abdulaziz City for Science and Technology, Missouri Univ. S&T), Ayodeji B. Alajo (Missouri Univ. S&T)

Study on Transmutation System of LLFP Using Fast Reactors

Toshio Wakabayashi, Makoto Takahashi (Tohoku Univ.), Satoshi Chiba (Tokyo Inst. Technol.), Naoyuki Takaki (Tokyo City Univ.), Yoshiaki Tachi (JAEA)

Fast Reactor Input Deck Generator (FRIDGe)

Ryan Stewart, Todd Palmer (Oregon State)

Loading Pattern Optimization Method Based on Discrete Differential Evolution

Guangyao Sun, Hui Ding, Bin Wu, Lijuan Hao, Pengcheng Long and FDS Team (Inst. of Nuclear Safety Technology)

Homogenization of TRISO Fuel Using Reactivity Equivalent Physical Transformation Method

Mohammad Alrwashdeh, Saeed A. Alamaeri, Ahmed K. Alkaabi, Mohamed Ali (Khalifa Univ.)

Two-Year PWR Core Design with Burnup and Enrichment Extension Using VERA-CS

Cole Blakely, Hongbin Zhang, Jianguo Yu (INL)

Evaluation of Updated Monte Carlo Models for the Penn State Breazeale Reactor

Benjamin Karl Harris, William J. Walters (Penn State)

Geometric Design Space for Sodium Fast Reactors

Ryan Stewart, Todd S. Palmer (Oregon State)

Current Progress on the Design of a Coupled Fast-Thermal Subcritical Assembly

John Pevey, Ond?ej Chvála, Sarah Davis, Vladimir Sobes, J. Wes Hines (ORNL)

Unstructured Mesh Unification for MCNP6.2 and PROTEUS in NEAMS Workbench

Peter J. Kowal, Kurt A. Dominesey, Mathieu N. Dupont, Jonathan A. Eugenio, Wei Ji (RPI)

FAST (Floating Absorber for Safety at Transient) for the Improved Safety of Metallic-Fuel-Loaded Sodium-Cooled Fast Reactors

Chihyung Kim, Yonghee Kim (KAIST)

Use of MCNP Surface Source Cards for Isotope Production Optimization

Emory Colvin (Center for Space Nuclear Research), Todd S. Palmer (Oregon State)

Stationarity Diagnostics for Monte Carlo Problems that Utilize Source Acceleration Schemes

Shikhar Kumar, Benoit Forget, Kord Smith (MIT)

Characterization, Operation, and Modeling of the MIT Graphite Exponential Pile

Sara Hauptman, Jarod Wilson, Kaichao Sun, Kord Smith, Benoit Forget (MIT)

Research Reactors in Support of Advanced Reactors R&D–Panel

Pavel Tsvetkov (Texas A&M)

The 2019 Edition of the IRPhEP Handbook

John D. Bess (INL), Tatiana Ivanova, Ian Hill (OECD), Lori Scott (INL)

Convolutional Neural Network for 2-D Assembly-Wise Pin Power Peaking Factor Prediction in PWRs

Lee Jinyoung, Nam Younduk (KEPCO)

Pin-Wise Convolutional Neural Network for MOC 3D Pin Power Prediction

Younduk Nam, Jin Young Lee (KEPCO)

Design Study on Fast Reactor with Low-Enriched Uranium Modeling Fuel at Kyoto University Critical Assembly

Kyoseong Song, Sanghoon Jang (Seoul National Univ.), Cheol Ho Pyeon, Masao Yamanaka (Kyoto Univ.), Hyung Jin Shim (Seoul National Univ.)

Effect of Doping Fuel with Beryllium on Accumulated Radiation Damage in a Breed-and-Burn Reactor

Kazuki Kuwagaki (U.C., Berkeley, Tokyo Inst. Technol.), Christopher Thomas Keckler, Massimiliano Fratoni (U.C., Berkeley)

Development of Wall Climbing Equipment for Dry Cask Storage System Inspection

Daewon Kim, Kyoungyong Noh, Kyoungwon Yoon, Misuk Jang, Seoung Rae Kim (Nuclear Engineering Service & Solution)

Design of Controllable Magnetic Wheel for Dry Cask Storage System Inspection Robot

Myounggyu D. Noh, Eusang Kwon, So Hee Park, Young-Woo Park

Safety and Safeguards by Design: Design of a Fuel Handling Device for Open-Pool Research Reactors

Bahram Nassersharif, Jonathan DeAlmeida, Seth Mace, Alex Harrington. Evan Ambrose (Univ. Rhode Island), Cameron Goodwin (Rhode Island Atomic Energy Commission), Carolynn P. Scherer (LANL)

Autonomous Radiation Mapping and Quantification Using an Unmanned Ground Vehicle

Anthony Abrahao (Florida International Univ.), Timothy Aucott (SRNL), Abdulmueen Alrashide, Joel Adams, Sebastian Zanlongo, Dwayne McDaniel, Leonel Lagos (Florida International Univ.)

Deployment of Time Resolved Particle Image Velocimetry Between Two PWR Surrogate Bundles

Roberto Capanna (George Washington Univ.), Lorenzo Longo, Fabienne Bazin, Guillaume Ricciardi (CEA), Philippe Bardet (George Washington Univ.)

Compressed Air Cannon for Relaxation Coefficient Measurements in Water Hammer

Roberto Capanna, Philippe Bardet (George Washington Univ.)

Experimental Study on the Coolability of Fuel Rods Under Forced Injection of Artificial Seawater

Seth C. Eckels, Zayed Ahmed, Daniel Franken, Steven J. Eckels, Hitesh Bindra (Kansas State)

Pool Boiling CHF Experiments Using Micron and Submicron Porous Silica Particles

Min Suk Lee, Dong Hoon Kam, Yong Hoon Jeong (KAIST)

The Research of Boiling Heat Transfer and CHF Correlation Derived on a Downward Facing Surface

Huai-En Hsieh, Hui-Fang Miao (Xiamen Univ.), Mei-Shiue Chen, Bau-Shei Pei (National Tsing Hua Univ.)

Development of a Non-Nuclear Microreactor Test Bed

D. P. Guillen (INL), H. Trellue (LANL), J. O’Brien, P. Sabharwall (INL), R. S. Reid (ORNL), T. Unruh (INL), T. Jay Harrison ORNL), T.-L. Sham (ANL)

Oxygen Concentration Measurements During the Initial Stages of an HTGR Double-Ended Guillotine Break

David J. Arcilesi Jr. (Univ. Idaho), Tae Kyu Ham (KHNP), Xiaodong Sun (Univ. Michigan), Richard N. Christensen (Univ. Idaho), Chang H. Oh (INL)

Non-Intrusive Velocity and Temperature Measurements of Buoyant Flows from Inductively Heated Dual-Spheres

Robert Muyshondt, Duy Thien Nguyen, Yassin Hassan, N. K. Anand (Texas A&M)

Lagrangian Velocity Measurements in a Pore-Scale of a Randomly Packed Bed Using Matching-Refractive-Index and Time-Resolved PTV Techniques

T. Nguyen, S. King, Y. A. Hassan (Texas A&M)

Preliminary Parametric Study for PCM Passive Cooling Heat Structure

Jai Oan Cho, Jaehyung Sim, Sung Gil Shin, Jeong Ik Lee (KAIST)

Measurement of Flow in a Mixing Tee Using Ultrasound Doppler Velocimetry for Opaque Fluids

Arturo Cabral (ANL, VCU), Sasan Bakhtiari, Thomas W. Elmer, Alexander Heifetz, Darius D. Lisowski (ANL), Lane B. Carasik (VCU)

Design of a High-Temperature Fluoride Salt Test Facility (HT-FSTF)

Sheng Zhang, Hsun-Chia Lin, Keyong Cheng, Xiaodong Sun (Univ. Michigan)

Fast Responding Pressure Sensitive Paint Measurements in a Helical Coil Steam Generator Model

Garland Alec Porter, Marilyn Delgado, Yassin Hassan (Texas A&M)

Design of Heat Pipe Test Facilities for Micro Reactor Applications

Minjee Cho, Benjamin Wang, Shanbin Shi (RPI)

Sliding Bubble Velocity Prediction on the Lower Part of a Horizontal Tube Heater Based on Force Balance Analysis

Jae Soon Kim, Yu-Na Kim (KAERI), Hyoung Kyu Cho (Seoul National Univ.)

Far Field Analysis of Helium/Air Mixing in Scaled-Down HTGR

Joseph Hafen, Jason Palmer, Richard Christensen (Univ. Idaho)

Wavelet Transform Analysis of Flow Field in a Helically Coiled Steam Generator Geometry

Saya Lee, Yassin A. Hassan (Texas A&M)

Response Time of Thermowells for Corrosive, High-Temperature Experiments

Denise Chavez, Ojasvin Arora, David Holler, Rodolfo Vaghetto, Yassin Hassan (Texas A&M)

Development of a Liquid Sodium Thermal Hydraulic Facility

Matthew Weathered, Tyler Sumner, Christopher Grandy (ANL)

Integration of the Nek5000 Computational Fluid Dynamics Code to the NEAMS Workbench: Modeling of the Turbulent Flow in a High-Flux Isotope Reactor Channel

Marc-Olivier G. Delchini, Robert A. Lefebvre, Mark L. Baird, Paul L. Miller, W. David Pointer (ORNL)

Lagrangian CFD Analyses of Airborne Particles from Dropped Shipping Containers for Use in DOE M441.1-1 Calculations

M. Alsharif (Consolidated Nuclear Security Y-12), Y. He, S. M. McGuffie (Porter McGuffie Inc.)

Computational Modeling of Flow Through Twisted Tape Geometry

Jack Fletcher, Monica Gehrig (Missouri Univ. Sci. & Technol.)

CFD Modeling of the Density Evolution Inside of the HENRI System

Silvino A. Balderrama, Guillaume P. Mignot, Wade R. Marcum (Oregon State), Nicolas E. Woolstenhulme (INL)

Application and Verification of the Nek5000 Regularized ?–? Turbulence Model to Pipe Flow using Higher-Order Data and PEPT Data

L. B. Carasik (FAST Research Group), C. Wiggins (FAST Research Group, U.T., Knoxville), D. R. Shaver (ANL)

Thermal Stratification Analysis for Sodium-cooled Fast Reactors: Development of the 1-D System Model

Cihang Lu, Zeyun Wu (VCU), James Schneider, Mark Anderson (U.W., Madison), Liangyu Xu, Emilio Baglietto (MIT), Matthew Bucknor, Matthew Weathered (ANL), Sarah Morgan (VCU), Sama Bilbao y Leon (OECD)

SAS4A Simulations of Post-Failure Fuel Relocation in the BI3 CABRI-1 Oxide Fuel Experiment

A. Tentner, A. Karahan (ANL), K. Kawada (JAEA)

A Theoretical Model for Diffusiophoresis in iPWR Containment Vessels

Rohan Biwalkar, Sola Talabi (Pittsburgh Technical), Kenneth Redus (Redus and Assoc.)

Overview of the Small Modular and Advanced Reactor Testing Center

Rohan Biwalkar, Sola Talabi (Pittsburgh Technical), Kenneth Redus (Redus and Assoc.)

Effect of the Thermal Expansion of the Used Nuclear Fuel Cask’s Basket on Temperature During Vacuum Drying

Megan Higley, Mustafa Hadj-Nacer, Miles Greiner (Univ. Nevada, Reno)

Modification of CUPID Code for Wall Condensation Phenomena in the Presence of Non-Condensable Gas Mixture Containing a Light Gas

Chang Won Lee, Hyoung Kyu Cho (Seoul National Univ.)

Density Wave Instability Verification of 1D Two-Fluid CFD Model

Krishna Chetty, Rita Appiah, Alexander Lopez-de-Bertodano, Christopher Sweeney, Subash Sharma (Purdue), John Buchanan (Naval Nuclear Lab.), Martin Lopez-de-Bertodano (Purdue)

Performance Evaluation of Accident Tolerant Fuels (ATF) and Reactor Core Isolation Cooling (RCIC) for Boiling Water Reactor

Jun Wang, Ryan Maurice Dailey, Michael Corradini (U.W., Madison)

Numerical Investigation to Validate Post-CHF Regimes with Droplet Breakup Behaviors in a 3-Field System Code

Seung Hyun Yoon, Kyung Doo Kim, Kwiseok Ha, Jaeseok Heo, Byung-Hyun You, Seung Wook Lee (KAERI)

Reduction of Steam Partial Pressure by Silica Gel Considering Free Volume

Dong Hoon Kam, Yong Hoon Jeong (KAIST)

Benchmarking GOTHIC to the Molten Salt Reactor Experiment

Rodney Harvill, Jeff Lane, John Link, Anita Gates (Zachry Nuclear Engineering)

Evaluation of S-Gamma and AMUSIG Models for Solving Population Balance Equation of Coupled Two-Fluid Model for Large Diameter Channel

S. Hong, J. P. Schlegel (Missouri Univ. Sci. & Technol.)

A Physics-Informed Machine Learning-Aided Framework for Predicting Departure from Nucleate Boiling in Rod Bundles

Xingang Zhao, Koroush Shirvan (INL), Robert K. Salko (ORNL)

One-Way Coupled Simulation of Twisted-Tube Bundle Flow-Induced Vibration

Landon Brockmeyer (ANL), Jerome Solberg (LLNL), Dillon Shaver (ANL), Elia Merzari (ANL)

Reduced-Order Modeling of Fluid Flows in Closed-Loop Systems

Péter German, Mauricio E. Tano, Jean C. Ragusa (Texas A&M), Carlo Fiorina (Ecole Polytechnique Federale de Lausanne)

Modelling of Fluel Assembly Under Dynamic Solicitation

Guillaume Ricciardi (CEA)

Leaky-Vessel Decay-Heat-Removal System for Fluid-Fuel Molten Salt Reactors

Charles Forsberg (MIT)

Validation of SAM Using CIET Experimental Data

Ling Zou, Rui Hu (ANL)

Using GOTHICTM and RAVEN to Explore Thermal-Hydraulic System Response

Patrick Skelton, Je?rey Lane (Zachry Nuclear Engineering)

Benchmark Exercise on Flow Mixing in Cold Leg of a Pressurized Water Reactor

Daniel Orea, Rodolfo Vaghetto, Thien Nguyen, Vasileios Kyriakopoulos, Yassin Hassan (Texas A&M)

Numerical Investigation of Molten Lead Flow in a Closed Loop to Estimate Pressure Demand

Khaled Talaat, Sang Lee (Univ. New Mexico), Youho Lee (Seoul National Univ.), Osman Anderoglu, Cemal Cakez, Shuprio Ghosh (Univ. New Mexico), Keith Woloshun, Seung Jun Kim, Stuart Maloy, Cetin Unal (LANL), Michael Ickes, Paolo Ferroni (Westinghouse)

Decay Heat in Nuclear Power Plants: Heat Exchanger Design and Evaluation Using Xchanger Suite® (Case Study)

Mohammad A. Hawila (Heat Transfer Research Inc.)

Sensitivity Analysis of Erosion/Deposition Coefficient for Crud Properties in Pressurized Water Reactors

Beomjun Jang, Chongkuk Chun (KEPCO)

Thermal-Hydraulic Analysis for Main Steam Line Break for Containment Pressure and Radioactivity Suppression System (CPRSS) of SMART Reactor

Kyung Jun Kang, Ji Han Chun, Jong Wook Kim, Han-Ok Kang (KAERI), Seong Su Jeon (FNC Technol. Co.), Keung Ku Kim, Moon Jung, Young-In Kim (KAERI)

Preliminary Design Study of Supercritical CO2 Cycle for Small Modular Reactor Application

Yoonhan Ahn, Yong Hwan Yoo (KAERI)

Fiber Optic Sensing Application in Quenching Temperature Measurement

Paul Hurley, Juliana P. Duarte (Virginia Tech)

Surface Characterization of Chromium Coated Zircaloy-4 Accident Tolerant Fuel Cladding Material

Rajnikant Umretiya, Robert Uhorchuk, Santiago Vargas, Carlos E. Castano, Jessika Rojas (VCU)

Influence of Surface Roughness on Wettability of Accident Tolerant Fuels Cladding

Robert Uhorchuk, Rajnikant Umretiya (VCU), Mark Anderson, Barret Elward (U.W., Madison), Sama Bilbao y Leon (VCU), Raul Rebak (GE), Jessika Rojas (VCU)

Best Estimate Plus Uncertainty Methods Applied to Hydraulic System Models

Daniel T. Gualandri, Jeffrey W. Lane (Zachry Nuclear Engineering)

Gas Migration Study for Glovebox Accident in a Process Room

Si Y. Lee (SRNL)

Best Estimate Plus Uncertainty Analysis for SBO

J. Ricardo Tavares de Sousa, Aya Diab (KEPCO)

Modeling and Simulations of HTGR During Pressurized Conduction Cooldown Transients Using SAM Code

Prasad Vegendla, Rui Hu, Ling Zou (ANL)

A Thermal-Mechanical Properties View of Impacts of Heater Materials on Critical Heat Flux

Mingfu He, Soon K. Lee, Amir Ali, Minghui Chen (Univ. New Mexico)

Verification of Lateral Conduction in Fuel Plates in PLTEMP/ANL Code

M. Kalimullah, A. P. Olson, S. H. Pham, J. R. Licht (ANL)

Assessment of Operator Action for SBO

J. Ricardo Tavares de Sousa, Aya Diab (KEPCO)

Acoustic Performance of Fluid-Filled Pipe with Periodic Helmholtz Resonator Considering Lateral Wall Elasticity

Qingna Zeng, Donghui Wang, Fenggang Zang, Yixiong Zhang (Nuclear Power Inst. China)

Importance of PIRT to the Safety of Heat Pipe Based Micro Nuclear Reactor

Jun Liao, Richard F. Wright (Westinghouse)

Thermal-Hydraulic Challenges for Micro-Reactors–Panel

Annalisa Manera (Univ. Michigan), Donna P. Guillen (INL)

Educational Nuclear Thermal Hydraulics Issues and Challenges–Panel

Elia Merzari (ANL)

Modelling Coolant Chemistry in the MYRRHA Reactor with a Multi-Physics Computational Tool

Alessandro Marino, Jun Lim, Alexander Aerts (SCK•CEN)

Optimizing Nuclear Signal Monitoring with Acoustically Tensioned Metastable Fluid Detector Technology

Nathan Boyle, Brian Archambault (Purdue), Rusi Taleyarkhan (Consultant)

Demonstration of a Data-Driven Approach for Error Estimation in Two-Phase Flow Simulation Using Coarse-Mesh CFD

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

Bubble Nucleation Characteristics in Subcooled Boiling Flow for Pressure Up to 600 kPa

Yang Zhao, Yu-Chen Lin (Purdue), Joshua P. Schlegel (Missouri Univ. Sci. & Technol.), Mamoru Ishii (Purdue), John R. Buchanan Jr. (Naval Nuclear Lab.)

Lagrangian Measurements in Pipe Flow via Positron Emission Particle Tracking

Cody Wiggins (U.T., Knoxville, Virginia Commonwealth), Lane Carasik (Virginia Commonwealth), Arthur Ruggles (U.T., Knoxville)

TRACE Simulation of a BWR Large Break LOCA with Zircaloy and Cr-Coated Cladding

Yue Jin (MIT), Xu Wu (NCSU), Koroush Shirvan (MIT)

Coupling of CUPID and nTER for Pin-by-Pin Subchannel Thermal-Hydraulics and Neutronics Analysis

Youyeon Choi, Hyoung Kyu Cho (Seoul National Univ.), Jin Young Cho (KAERI)

Preliminary Investigation of Fuel Rod Burst Potential Under LBLOCA with Burnup Extension

Hongbin Zhang, Cole Blakely, Jianguo Yu (INL)

Thermal Analysis of a Heat Pipe Cooled Reactor Core Based Unit Assembly Using Coupled FLUENT and ANLHTP

San Lee, Hyoung Kyu Cho (Seoul National Univ.), Changho Lee, Taek K. Kim (ANL)

Preliminary Design Evaluation of a Natural Circulation Molten Salt Irradiation Loop

Sandesh Bhaskar, Abdalla Abou-Jaoude (INL)

Experimental Investigation of Local Fluid Temperature Profiles in Sub-Cooled Boiling Flows

Zhuoran Dang, Yang Zhao (Purdue), Jingyu Du (Purdue, Tsinghua Univ.) Mamoru Ishii (Purdue)

An Entrainment Rate Correlation for Annular Flow

Guanyi Wang (Purdue), Pravin Sawant (NuScale), Mamoru Ishii (Purdue)

Effect of Break Size on Flow Instabilities in a PWR-type Small Modular Reactor

Yu-Chen Lin, Akshay Kumar Khandelwal (Purdue), Sipeng Wang (Purdue, Xi'an Jiaotong Univ.), Mamoru Ishii (Purdue)

Potential Flow Model for Seismic Excitation of PWR Assemblies Under Axial Flow

Roberto Capanna, Guillaume Ricciardi (CEA), Emmanuelle Sarrouy, Christophe Eloy (Aix Marseille Univ.)

Pitch your PHD–Panel

Nicolas Stauff (ANL)

Diversity and Inclusion in Nuclear–Panel

Kalin Kiesling (U.W., Madison)

How to Give Technical Presentations–Panel

Kelsey Amundson

The Fastest Path to Achieving Zero-Emissions: Nuclear’s Role–Panel

Harsh Desai (NEI)

Nuclear Advocacy—Storm the Hill Training—I–Panel

Eric Meyer (Generation Atomic)

Nuclear Advocacy—Storm the Hill Training—II–Panel

Eric Meyer (Generation Atomic)