Annual Meeting 2018 / Volume 118

Table of Contents

Author Index

Full Issue

Opening Plenary: New Build and Power Upgrade

ANS President's Special Session: What Nuclear Needs

General Chair's Special Session: Small Modular Reactors

Delivering the Nuclear Promise-Panel

Recent Advances in Decommissioning of Nuclear Plants-Panel

Novel Ion Accelerator for Nuclear Physics Research

Yong Jiang, Jay Hirshfield (Yale)

Niowave Neutron Interrogation System

W. A. Peters, M. Mamtimin, C. H. Boulware, T. L. Grimm, F. Y. Odeh, V. N. Starovoitova (Niowave, Inc.), S. A. Pozzi (Univ. Michigan), A. Inglis (Silverside Detectors)

Improved Transmission and Capture Data for Tantalum-181

J. M. Brown (RPI), G. Leinweber, D. P. Barry, B. Epping, M. Rapp (Naval Nuclear Lab.), Y. Danon (RPI)

Comparison of Incident and Modulated Neutron Flux Inside a High Flux Neutron Generator in the Presence of a Polyethylene Shield

Nnaemeka Nnamani (Univ. Calif., Berkeley)

Characterization of Spark Plasma Sintered W/UO2

Dennis Tucker (NASA), Yaqiao Wu, Jatuporn Burns (Boise State)

Study of Film Cooling in Diverging Section of Nuclear Rocket Nozzle

Xiaokai Sun, Wei Peng, Jie Wang (Tsinghua Univ.)

Early Introduction of Computational Methods in Undergraduate Nuclear Engineering

Kenneth S. Allen, Blake K. Huff (U.S. Military Academy)

Human Capital Development, Safeguards by Design, and University Engagement-Lessons Learned

Carolynn P. Scherer, Eric B. Rauch, Christy Ruggiero (LANL)

Nuclear Quality Assurance for Universities

James C. Kendrick, Per F. Peterson (Univ. Calif., Berkeley)

Role-Focused Training and Education in the UK Defense Nuclear Enterprise

Kirk D. Atkinson, Alice M. Darbyshire, Farkhanda Kauser, Rizgar Mella, Martyn D. Kendrick, James R. Bratt (Defence Academy U.K)

A Nuclear Power Plant Re-Shapes Culture to Improve Performance

Lynne Viscio and Tanya Mann (MGStrategy)

Manage Moments of Truth to Improve Plant Performance

Tanya Mann, Lynne Viscio (MGStrategy)

Backscatter Surrogate for Highly Enriched Uranium

Nicholas Anthony Costa (US Naval Academy)

Analysis and Comparison of In-Situ Corrosion Rate Measurements with Co-Located Analytical Soil Corrosivity Parameters Along Buried Pipelines at Nuclear Power Facilities

M. E. Darois (RSCS Inc.), CGWP, H. G. Kleinfelder (CorrTech Inc.)

PHR Capacity Analysis of Nuclear Heating Reactor HAPPY 200

Mian Xing, Zhaocan Meng, Yaodong Chen (State Power Investment Corp. Research Inst.)

Particle Image Velocimetry (PIV) Measurements in 1/23 Scaled Water Reactor Cavity Cooling System (WRCCS)

N. Quintanar, T. Nguyen, R. Vaghetto, Y. Hassan (Texas A&M)

Focus on Communications: It's All About The Plant-Panel

Status on Repository Concepts Internationally-Panel

Determination of Mechanisms and Kinetics of Ag0Z and Ag0-Aerogel Aging in Nuclear Off-Gases

Yue Nan, Seungrag Choi (Syracuse), Austin P. Ladshaw Sotira Yiacoumi, Costas Tsouris (Georgia Tech. & ORNL), Lawrence L. Tavlarides (Syracuse)

Effects of Changing Parameters on Chlorination Process of Rare Earth Metals and Actinides Mixture

Parker Okabe (Univ. Utah), Devin Rappleye (LLNL), Michael Simpson (Univ. Utah)

Electrochemical Methods for Continuous Metal Corrosion Monitoring in Molten Salts

D. Horvath, P. Bagri, M. F. Simpson (Univ. Utah)

Effect of Electrodes and Salts Impurity on the Cyclic Voltammetry in Molten Li2O/LiCl

Meng Shi (Univ. Idaho), Shelly Li (INL), Haiyan Zhao (Univ. Idaho)

Diffusion Model and Artificial Neural Intelligence (ANI) Comparison for Cyclic Voltammetry Prediction of Uranium and Zirconium Chloride in LiCl-KCl Eutectic Salt

Samaneh Rakhshan Pouri, Supathorn Phongikaroon, Zeyun Wu (Virginia Commonwealth)

Upgrades on High Reliability Safeguards Model for Material Throughput in Fuel Fabrication

Jieun Lee , R. A. Borrelli (Univ. Idaho)

Closing the Nuclear Fuel Cycle: Molten Salt Reactors

Kyra Lawson, Mohammad Modarres (Univ. Maryland)

Advanced Closed Fuel Cycles?The Economic Challenge?Panel

Technical Grand Challenges?Closing the Nuclear Fuel Cycle?Panel

Developing a Molten Salt Reactor Safeguards Model

Benjamin B. Cipiti, Nathan Shoman (SNL)

Modeling Molten Salt Performance in MSRs: Using Thermochemical Behavior

Theodore M. Besmann, Johnathan C. Ard (Univ. South Carolina), Jacob W. McMurray (ORNL)

Chemistry of Molten Salt Reactor Fuel Salt Candidates

Pavel Sou?ek, Ond?ej Bene

On the Possibility of Quantitative Electrochemical Separation of Uranium from Gadolinium in Fluoride Melts

Martin Straka, Lorant Szatm

Galvanic Reduction for Actinide Recycling in a Molten Chloride Fast Reactor

Prashant Bagri, Michael Simpson (Univ. Utah)

Wetting of Graphite by Molten Fluoride Salts: Initial Experiments

Alexandra R. Delmore, Will Derdeyn, Ruchi Gakhar, Raluca O. Scarlat (Univ. Wisconsin, Madison)

Design and Fabrication of Molten Salt Loop for Material Corrosion and Salt Chemistry Control

Brendan Dsouza, Jinsuo Zhang, Shaoqiang Guo (Virginia Tech)

Small Scale Recycling of Irradiated Nuclear Fuel for Isotope Production and Nuclear Energy R&D

K. A. Shannon, T. L. Grimm, A. K. Grimm, N. C. Johnson, F. Y. Odeh, V. N. Starovoitova (Niowave Inc.), P. Kozak, A. V. Gelis (ANL)

Extraction of Actinides from Nitric Acid Solutions by Using N,N-di(2-ethylhexyl)-diglycolamic Acid

Guoxin Tian (China Inst. Atomic Energy & Harbin Eng. Univ.), Yan Zhang, Suliang Yang (China Inst. Atomic Energy)

Micro Scale Monitoring and Analysis of Phase Transfer Kinetics During Solvent Extraction

Susan Howett, Amanda Casella, Amanda Lines, Danny Bottenus, Forrest Heller, Sue Clark (PNNL), Calvin Delegard (TradeWind Services), Gilbert Nelson (College of Idaho), Sam Bryan (PNNL)

Verifying Contents of Dry Fuel Casks with Multiple Coulomb Scattering of Cosmic Ray Muons

Daniel Poulson (LANL)

Design of a Borated Aluminum Cask for Onsite Used Fuel Storage

J. Seth Dustin (Univ. Idaho), Samuel Pedersen, Brian J. Jaques (Boise State), R. A. Borrelli (Univ. Idaho)

Regulatory Licensing Pathway for a Borated Aluminum Cask Design for Onsite Used Fuel Storage

R. A. Borrelli (Univ. Idaho), Mark S. Delligatti (Table Rock, LLC.)

A Criticality Analysis of a Dry Storage Cask with Advanced Nuclear Fuel Cask Additive

J. Bae, R. Bean (Purdue), R. Abboud (RGA Labs, Inc.)

Development of a Greedy Method for Used Fuel Selection in Dry Cask Storage

Kristina Yancey Spencer, Pavel V. Tsvetkov, Joshua J. Jarrell (Texas A&M)

Comprehensive Evaluation System for 137Cs Migration and Radiation Levels in Eastern Fukushima Prefecture

Akihiro Kitamura, Kazuki Iijima (JAEA)

Preliminary Radioactive Contamination Assessment for Decommissioning on Kori-Unit 1 Bioshield

Donghyun Lee, Hee Reyoung Kim (UNIST)

Design and Fabrication of a Heat Treatment Oven for Full-Length Spent Nuclear Fuel Rods

Rose Montgomery, Nesrin Cetiner (ORNL), Charles Blue, Randall Blue (Infrared Heating Technol.), Bruce Bevard (ORNL)

Fuel Cycle for a Uranium-Plutonium Thermal Breeder Reactor

Neal L. Mann (Consultant)

Mechanical Integrity of Spent Nuclear Fuel Rods

Efstathios Vlassopoulos (EPFL), Stefano Caruso (NAGRA), Konrad Linnemnn (BAM), Ramil Nasyrow, Ralf Gretter, Lorenzo Fongaro, Dimitrios Papaioannou (European Commission)

Correlation Between Strain and Buckling of Spacer Grid by Side Impact

Kyungho Yoon, Jaeyong Kim, Hongryeol Oh, Donghak Kook (KAERI)

Experimental Methods for Determining Li2O Entrainment in Electrolytic Uranium Oxide Reduction

A. J. Burak, M. F. Simpson (Univ. Utah)

Visually Determining the Thermal Expansion of a Triple Bubbler System in Pyroprocessing Molten Salt

Amey Shigrekar (Univ. Idaho), Ammon Williams, Greg Galbreth (INL)

Challenges Associated with the Back End of the Molten Salt Reactor Fuel Cycle-Panel

Investigations into the Gas Phase Reactions of Zirconium Tetrachloride (ZrCl4) from UNF Cladding

Craig Barnes, Austin Albert (Univ. Tenn.), Guillermo Daniel DelCul (ORNL), David F. McLaughlin (Westinghouse)

Computational Studies of Gas Phase Reactions of Zirconium Tetrachloride (ZrCl4) and Metal Chloride Impurities

Michael Orick, Craig Barnes (Univ. Tenn.), Guillermo Daniel DelCul (ORNL), David F. McLaughlin (Westinghouse)

Ab Initio Study of Zirconium(IV) Chloride

Eunja Kim (Univ. Nevada, Las Vegas), Philippe F. Weck (SNL), Rosendo Borjas, Eswari Balasekaran, Frederic Poineau (Univ. Nevada, Las Vegas)

Burning LWR SNF On-Site with Mu*STAR Accelerator-Driven Molten-Salt Systems

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

Evaluation of Various Methods for Converting Spent Nuclear Fuel into Fluoride Salts

P. A. Taylor, A. D. Braatz, G. D. Del Cul, B. B. Spencer (ORNL)

Fuel Cycle Analysis of an Innovative Lead-Cooled Subcritical System

Xuewei Fu, Minghuang Wang, Yunqing Bai (Chinese Academy of Sciences)

Physics Evaluation of Thorium-Based Internally-Cooled Annular Fuel Bundles for Use in Pressure-Tube Heavy Water Reactors

B. P. Bromley, K. Groves, A. Colton, S. Golesorkhi (CNL)

Testing the Relative Oxidizing Hazard of Organic Wipes

J. F. Lucchini, C. J. Chancellor, B. A. Crawford, B. E. Ams, C. Poulos, D. Weaver (LANL)

The Value of Independent Environmental Monitoring in Nuclear Waste Disposal: A WIPP Case Study

P. Thakur (Carlsbad Environmental Monitoring & Research Center)

Thermo-Hydro-Mechanical Evaluation of Critical Mass in Repository Far-Field

Alex Salazar, Massimiliano Fratoni (Univ. Calif., Berkeley)

Water Migration in Engineered Barrier Materials for Radioactive Waste Disposal

J. McFarlane, R. E. Hale (ORNL), V. H. DiStefano (ORNL & Univ. Tenn.), L. M. Anovitz, H. Z. Bilheux, M. C. Cheshire, L. L. Daemen, R. L. Howard (ORNL), E. Perfect, D. S. Hussey, D. L. Jacobson, J. M. LaManna (NIST)

WIPP Safety Significant Confinement Ventilation Pre-Treatment Design

Richard Berry, Jack Clemmens (APTIM Federal Services), Rodney Whisenhunt (Nuclear Waste Partnership)

Challenges of Digital I&C Technology-I-Panel

Research on the Methodology of Verification of Vital Digital Assets

Yeeun Byun, Siwon Kim, Kookheui Kwon (Korea Institute of Nuclear Nonproliferation and Control)

Simultaneous Test of Graphic Recorders (KR-2000 and KR-3000) with I/O Stimulator

Jang-Yeol Kim, Chang-Hwoi Kim (KAERI)

The Development of Safety DCS Platform - NicSys

Liu Zhikai, Hu Yiwu (China Nucl. Control System Eng. Co.)

How EMI/RFI Site Surveys Can Improve the Digital Upgrade Process

Chad Kiger, Zachary Crane (AMS Corp.), Mark Campbell (Talen Energy)

Assessing the EMI/RFI Risks of Wireless Devices Using a Cognitive Radio System

Chad J. Kiger (AMS Corp.), William Ansley, Andrew Watters (Exelon), Chris Lowe (AMS Corp.)

Development of Simulation-Based Test-Bed for Nuclear Power Plant Safety-Critical Software

Sang Hun Lee (RPI), Seung Jun Lee (UNIST), Jinkyun Park (KAERI), Eun-chan Lee (Korea Hydro & Nuclear Power Co.), Hyun Gook Kang (RPI)

Development of a Methodology for Quantifying the Amount of Additional S/W V&V Processes: When Cyber Security Techniques are Applied to NPP I&C Systems

Chanyoung Lee, Poong Hyun Seong (KAIST)

Licensing and Implementation of Digital I&C at Research Reactors-Panel

Development, Fabrication, and Testing of a Prototype High Temperature Fission Chamber

Padhraic L. Mulligan, N. Dianne B. Ezell, Christian Petrie, Lou Qualls (ORNL), Neil Taylor (Ohio State)

Development and Testing of a High-Speed Fiber-Based Pyrometer for TREAT

Austin Fleming, Colby Jensen (INL)

In-Core Evaluation of Online Instrumentation in the TREAT Reactor

Kevin Tsai, Colby Jensen, Troy Unruh, Austin Fleming, Cody Race (INL)

Suggestion of the Eye-Tracking System Based Fitness-for-Duty Evaluation Methodology in Nuclear Power Plants

Moon Kyoung Choi, Poong Hyun Seong (KAIST)

Human System Interface Improvements Using Advanced Keyboard-Video-Mouse (KVM) Technology

Richard Turk (Technology Resources, LLC), Richard Cooper (Thinklogical, LLC), Bradley Yeates (Southern Co.)

Evolving Nuclear Power Generation Through Optimized Asset Performance Management

Levon Keusseyan (GE Hitachi)

Robust Online Monitoring Technologies for Nuclear Power Plant Sensors

P. Ramuhalli (PNNL), J. Coble (Univ. Tenn.), B. Shumaker (AMS Corp.)

A DTW Based Automatic Transient Identification Method in Nuclear Power Plants

Xiaoming Bai, Honglei Ai, Xinjun Wang (Nuclear Power Institute of China)

Management of Aging of Reactor Internal Components

B. D. Shumaker, H. M. Hashemian, C. J. Kiger, A. H. Hashemian (AMS)

Model Learning with the CIET Facility Heater

Christopher Poresky, Per F. Peterson (Univ. Calif., Berkeley)

Neural Network-Based Predictive Control for the Thermal Power of a MHTGR-Based NSSS

Zhe Dong, Miao Liu, Zuoyi Zhang, Yujie Dong, Xiaojin Huang (Tsinghua Univ.)

MCNP Detector Simulations with DRiFT's Digitizer Class

M. T. Andrews (LANL)

Design Optimization of a Neutron Activation Based Explosives Detection System

Zafar ullah Koreshi, Hamda Khan (Air Univ.)

CR-39 Detector Irradiated by Different Radiation Particles and Its Applications

Zhiheng Xu (Nanjing Univ.), Erik Ziehm (Univ. Illinois, Urbana-Champaign), Matthew Bergschneider (Industrial Heat, LLC.), George H. Miley (Univ. Illinois, Urbana-Champaign)

New Core-Moderator Assembly and Neutron Beam Ports Development and Installation at the Radiation Science and Engineering Center

Kenan

Digital Control and Safety System Modernization for the Penn State TRIGA Reactor

James Turso, Kenan

Breaking the Digital Ceiling: Research Reactors Driving Innovation

R. Bean, C. Townsend (Purdue), R. Ray (Mirion Technologies)

Methodology Development for Cybersecurity Vulnerability Assessment of University Research Reactors

S. A. Lassell, A. I. Hawari (NCSU), J. S. Benjamin, K. T. Barnes, V. L. Wright (INL)

Licensing Process for Upgrading I&C Systems at Nonpower Production or Utilization Facilities (NPUFs)

D. A. Hardesty (U.S. NRC), M. D. Muhlheim (ORNL), N. Carte, R. Alvarado, P. G. Boyle, D. Warner, A. Adams (U.S. NRC)

Production of Alpha and Beta Radioisotopes for Nuclear Batteries Using a Superconducting Electron Linac

V. N. Starovoitova, T. L. Grimm, A. K. Grimm, F. Y. Odeh, W. A. Peters (Niowave, Inc.), A. Afanasev, N. Guardala (George Washington Univ.), J. Carroll, M. Litz (U.S. Army Research Lab.), T. Adams (Naval Surface Warfare Center), S. Maximenko (U.S. Naval Research Lab.)

A Python-Based ENDF Cross Section Explorer

H. Omar Wooten (LANL)

Quantitative Crack Analysis Using Neutron Radiography with Gadolinium Contrast Enhancement Agents

Russell Jarmer, Jeffrey C. King (Colorado School of Mines), Aaron Craft, Robert O'Brien (INL)

Characterizing Neutron Scatter in a Correlated Fission Experiment

Tyler A. Jordan (Univ. Calif., Berkeley & LANL), Madison T. Andrews, Krista C. Meierbachtol, Patrick M. Talou (LANL)

Modeling and Simulation of a Ring Geometry CdZnTe Detector for Medical Imaging Applications

O. Dim (BNL & Univ. Mass.), Y. Cui (BNL), Y. Seo (Univ. Calif.), S. K. Aghara (Univ. Mass.)

Current Issues in Computational Methods-Roundtable

An Efficient Sweep-Based Solver for the SN Equations on High-Order Meshes

Terry S. Haut, Peter G. Maginot, Vladimir Z. Tomov, Thomas A. Brunner, Teresa S. Bailey (LLNL)

Convergence of Sequential and Parallel One-Node CMFD Accelerations for Neutron Transport Analysis

HyeonTae Kim, Yonghee Kim (KAIST)

Improved Performance of the PN Scattering MOC Solvers in MPACT

Shane Stimpson, Benjamin Collins (ORNL)

Solution of the Neutron Survival Probability Equation by the Eigenfunction Expansion Technique

Patrick F. O'Rourke, Anil K. Prinja (Univ. New Mexico)

A Multilevel Quasidiffusion Method with Hybrid Temporal Discretization for Thermal Radiative Transfer Problems

Pedram Ghassemi, Dmitriy Anistratov (NCSU)

Effective Use of the Linear Fine Mesh Rebalance for the DSA of SN Transport Equation with Tetrahedral Meshes

Habib Muhammad, Ser Gi Hong (Kyung Hee Univ.)

Emissivity-Limited Implicit Monte Carlo

Ryan T. Wollaeger, Mathew A. Cleveland, HyeongKae Park (LANL)

Time Step Control for Iterative Multifrequency Corrected Implicit Monte Carlo

Mathew Cleveland, Ryan Wollaeger, Andrew Till (INL)

An Optimal-Cost Monte Carlo Approach to Stochastic Media Transport Calculations

Aaron J. Olson, Brian C. Franke (SNL)

MonteRay?A Prototype Software Library for Accelerating Monte Carlo Particle Transport on GPU Hardware

Jeremy E. Sweezy (LANL)

Continuous-Energy Monte Carlo on GPUs in Shift

Steven P. Hamilton, Thomas M. Evans, Stuart R. Slattery (ORNL)

Monte Carlo Tally Convergence: Runtime Comparisons Between Functional Expansion Tallies and Mesh Tallies

Brycen Wendt (Idaho State), Leslie Kerby (Idaho State & INL)

On the Connection Between Sensitivity and Identifiability for Inverse Uncertainty Quantification

Xu Wu, Koroush Shirvan (MIT), Tomasz Kozlowski (Univ. Illinois, Champaig-Urbana)

Global Sensitivity Analyses on Coupled VERA-CS/BISON and VERA-CS/FRAPCON Simulations

Hongbin Zhang (INL)

Bayesian Calibration and Uncertainty Quantification for TRACE Based on PSBT Benchmark

Chen Wang (Univ. Illinois, Urbana-Champaign), Xu Wu (MIT), Katarzyna Borowiec, Tomasz Kozlowski (Univ. Illinois, Urbana-Champaign)

Validating TRACE Void Fraction Predictive Capability Using the Quantitative Area Validation Metric

Xu Wu, Koroush Shirvan (MIT), Tomasz Kozlowski (Univ. Illinois, Urbana-Champaign)

Automatic Selection of High-Fidelity Models and Surrogates for Uncertainty Analysis

Congjian Wang, Andrea Alfonsi, Diego Mandelli, Paul W. Talbot, Cristian Rabiti (INL)

First-Order Perturbation for Uncertainty Quantification in the Deterministic Truncation of Monte Carlo Method

Hyeontae Kim, Inhyung Kim, Yonghee Kim (KAIST)

A New Uncertainty Evaluation Method for SFP Criticality Calculation

Kazuya Yamaji, Tetsuya Sugimura, Yasuhiro Harada, Daisuke Sato, Shinya Kosaka (Mitsubishi Heavy Industries, Ltd.)

Inverse Uncertainty Quantification of TRACE Physical Model Parameters Using BFBT Benchmark with Investigation of Measurement Bias

Katarzyna Borowiec, Tomasz Kozlowski (Univ. Illinois, Urbana-Champaign)

An Eigenvalue Extension to the Candlestick Analytic Space- Time Depletion Benchmark and Its Application to Monte Carlo Simulation

Gabriel Kooreman, David P. Griesheimer (Naval Nuclear Lab.)

An Analytical Model that Shows Possible Bias in Opacity Measurements

Todd Urbatsch (LANL)

Solution of One-Speed Homogeneous Slab Transport Problems via Orthogonal Expansion of Emission Density

Kyle Remley (Naval Nuclear Lab.)

Metaheuristic Optimization Method for Neutron Spectra Shaping

Sandra Bogetic (Univ. Calif., Berkeley), James E. Bevins (Air Force Inst. Technol.), Lee A. Bernstein (Univ. Calif., Berkeley & LLNL), Rachel Slaybaugh, Jasmina Vujic (Univ. Calif., Berkeley)

Comparison Between Gaussian Processes and DMD Surrogates for Isotopic Composition Prediction

Rabab Elzohery, Mohammad Abdo, Jeremy Roberts (Kansas State)

A Reduced-Order Model for the Solution of Diffusion Equations

Jaron P. Senecal, Wei Ji (RPI)

Model Verification via Principal Component Analysis

Bassam A. Khuwaileh (Univ. Sharjah)

Technical Basis for the Uranium Processing Facility Criticality Accident Alarm System

C. E. Gross (Paschal Solutions, Inc.), R. S. Brown (Gem Technologies, Inc.), K. H. Reynolds (Y-12 National Security Complex), R G. Taylor (C. S. Engineering Inc.)

MCNP 6.1.1 Validation for Shielding Applications

Timothy D. Jackson (Consolidated Nuclear Services)

The Y-12 Legacy Criticality Accident Alarm System

Chris Haught, Chris Woodrow (Consolidated Nuclear Security)

Swapped Source": A Forward Calculation Technique to Help Establish the Worst-Case Accident Location for CAAS Detectors in Fixed Locations

C. E. Gross (Paschal Solutions, Inc.), R. S. Brown (Gem Technologies, Inc.), K. H. Reynolds (Y-12 National Security Complex), R G. Taylor (C. S. Engineering Inc.)

Criticality Accident Alarm System Removal Methodologies

Tom Hines (DOE), Matthew Wilson (Paschal Solutions Inc.)

Is an ANS-8.3 Compliant CAAS Justifiable: Time to Recognize Reality

Thomas P. McLaughlin (Retired)

Enhancing the Criticality Safety Analysis for the Mobile Plutonium Facility

Tracy Stover, Steve Kessler, John Dewes (SRS)

Development of Augmented Reality Technology for Nuclear Criticality Safety Applications at Los Alamos National Laboratory

Austin Meredith, Andrew Wysong, Julio Trujillo (LANL)

Elimination of Acid Based Criticality Scenarios in the HM-Process

Tracy Stover, John Lint, W. Glynn Dyer (SRS)

Preliminary Design of Temperature Dependent Critical Experiments at Atmospheric Pressure with Low Enriched UO2 Fuel

Mathieu Dupont (RPI), Thomas M. Miller (ORNL)

Reactivity Simulation for Criticality Safety Training and Future Projects at LANL

Jacob McCallum, Dave Miko, Julio Trujillo, Andrew Wysong (LANL)

Criticality Characterization of Plutonium?Iron Systems

Arielle Miller, Jerry McKamy (DNFSB)

Nuclear Criticality Safety Strategy for the Downgrade of the 9206 Facility

Austin McGee, Michael Crouse (Consolidated Nuclear Security)

The 2018 Edition of the ICSBEP Handbook

John D. Bess (INL), Tatiana Ivanova, Ian Hill (OECD), Margaret A. Marshall (INL)

Criticality Safety Scenario-Based Training at Los Alamos National Laboratory

Mary Beth Lujan, Julio Trujillo, Andrew R. Wysong (LANL)

A First Look at the Thermal Neutron Scattering Law for H-UH3

Michael L. Zerkle (Naval Nuclear Lab.)

Sloped Bottom Tanks and Areal Density?Part I: Case Study in H-Canyon Decanter Controls

Tracy Stover, John Lint, Meagan Strachan (SRS)

Sloped Bottom Tanks and Areal Density - Part II: Functional Behavior of Projected Areal Density

Tracy Stover (SRS)

Benchmark Model Temperatures Incorporated into DICE

Z. J. Clifton (Univ. Alabama, Huntsville), W. J. Marshall (ORNL), I. Hill (Nuclear Energy Agency)

Crediting a Soluble Neutron Absorber at Y-12 Under ANSI/ANS-8.14-2004

V. B. Lollar (Consolidated Nuclear Security), A. W. Krass (C. S. Engineering, Inc.)

Temperature Measurements of the BeRP Ball During the Subcritical Copper-Reflected ?-Phase Plutonium (SCR?P) Experiment

T. Cutler, R. Bahran, J. Hutchinson (LANL)

The Case for and Against a Gadolinium Bias in SCALE: Opening Arguments

W. J. Marshall (ORNL)

Estimating Computational Biases for Criticality Safety Applications with Few Neutronically Similar Benchmarks

C. M. Perfetti, B. T. Rearden, W. J. Marshall (ORNL)

Effect of Corner Reflection on the Critical Mass of Plutonium

Quinton Beaulieu, Natasha Glazener (LANL)

Ensuring the Fidelity of Data Assimilation Methodology Bias Estimates

C. M. Perfetti, B. T. Rearden (ORNL)

Validation of KENO V.a and KENO-VI in SCALE 6.2.2 Using ENDF/B-VII.0 and ENDF/BVII.I Libraries

E. M. Saylor, W. J. Marshall (ORNL), Z. J. Clifton (Univ. Alabama, Huntsville), J. B. Clarity, B. T. Rearden (ORNL)

ANS 8.10 Criteria for Nuclear Criticality Safety Controls in Operations with Shielding and Confinement, Uses and Purpose-Panel

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

ANS-8 Standards Forum

Insight into Thermal Aging of Jacket-Bonded Ethylene-Propylene Rubber Cable Insulation

Leonard S. Fifield (PNNL, Washington State), Miguel Correa, Yongsoon Shin, Andy J. Zwoster (PNNL)

Multi-Sectioned Kinetics for the Degradation of Cable Insulation

Yuan-Shang Chang, Ali Mosleh (UCLA)

Avoiding Unnecessary Cable Replacement in Nuclear Power Plants

C. Kiger, C. Sexton, H. Hashemian, T. Toll (Analysis and Measurement Services Corp.), L. Dormann, W. Wasfy (Exelon)

Research Gap in Management of Insulation Aging of Medium Voltage Cables in Nuclear Power Plants

C. J. Kiger, H. M. Hashemian, C. D. Sexton, T. A. Toll (Analysis and Measurement Corp.)

Cable Insulation Testing for Mechanistic Degradation FEA Modeling

Brian Hinderliter, Elizabeth Hill, Melissa Maurer-Jones, Alexander Carlberg, Taylor Hebner (Univ. Minnesota, Duluth), Robert C. Duckworth (ORNL)

Defect Length and Profile Influence on Frequency Domain Reflectometry

S. W. Glass, L. S. Fifield, A. M. Jones, T. S. Hartman (PNNL)

Electrical Insulation Test on Mock-Up Helium Circulator for HTR-PM

Gang Zhao, Ping Ye, Hong Wang (Tsinghua Univ.)

Establishing the Criteria for the Evaluation Active vs Passive Safety Systems

Luciano Burgazzi (ENEA)

NuScale Power Plant Resilience

Jose N. Reyes, Daniel T. Ingersoll (NuScale)

Study on Diversity Actuation Signal of DAS for ACP100

Dan Zhang (Nuclear Power Institute of China)

Experimental Nucleate Pool Boiling on a Horizontal Plate in Saturated Water

Yong-Han Chang , Tien-Juei Chuang , Yuh-Ming Ferng (Tsing Hua Univ.)

An Explanation of the Damage in the Fukushima 1F3 Exploslion

Robert E. Henry (Fauske & Associates)

Experience with Severe Accident Management Review Missions at Nuclear Power Plants

George Vayssier (NSC Netherlands)

Sensitivity Analyses of a Type A Transportation Package

J. J. Carbajo, P. K. Jain, B. D. Patton, S. M. Robinson (ORNL)

Uncertainty Quantifications for the MIT Reactor Thermal-Hydraulic Analysis

Yu-Jou Wang, Kaichao Sun, Lin-Wen Hu (MIT)

Preserving Key Nuclear Safety Data-Panel

Integration of Fault-Trees and Event-Trees into Dynamic PRA

D. Mandelli, D. Maljovec, A. Alfonsi, C. Wang, Z. Ma, C. Parisi, C. Smith (INL)

Development of Domestic Risk Informed Decision Making Framework

Dongju Jang, Namchul Cho, Sok Chul Kim (Korea Inst. Nucl. Safety)

A Sensitivity Study on Population Segmentation Effects in the MACCS Code

Wonjong Song, Byeongmun Ahn, Yein Seo, Moosung Jae (Hanyang Univ.)

Use of Decision Trees for Evaluating Severe Accident Management Strategies

Sunghyun Park, Hoyoung Shin, Moosung Jae (Hanyang Univ.)

Development of Safety Significance Analysis System for Risk-Informed Decision Making

Bo Gyung Kim, Dongju Jang, Namchul Cho, Sok chul Kim (Korea Inst. Nucl. Safety), Yongsuk Lee, YoungChul Cho (FNC Technol. Co., Ltd.)

Dynamic Fault Tree Analysis for NPP Emergency Diesel Generator System

Daochuan Ge, Shanqi Chen, Zhen Wang, Zhibin Chen (Chinese Academy of Sciences)

A Study on the Design Requirement for the Level 3 PSA Code Development

Sunhee Park, Han Seok-Jung, Sung-Yeop Kim (KAERI)

Modeling of Aggressive Cool Down in a PSA with a Procedural Change

Wondea Jung, Jaehyun Cho (KAERI)

Safety Aspects of Accident Tolerant Fuels-Panel

Licensing of Medical Isotope Production Facility-Panel

Export Controls-Panel

Status and Emerging Developments in the Management of Used Nuclear Fuel-Panel

Additive Manufacturing: A Review of Export Controls and Nuclear Nonproliferation Challenges

Lauren Boldon, Farnaz Alimehri (ANL)

Modeling Potential JCPOA Diversion Scenarios with Cyclus

Baptiste Mouginot, Kathryn Mummah, Paul P. H. Wilson (Univ. Wisconsin, Madison)

An Overview of Nonproliferation Workshops at Oak Ridge National Laboratory: 2013-2017

Jessica L. White-Horton, J. Michael Whitaker, S. K. Smith (ORNL), K. V. Gilligan (BNL)

Production of Radioxenon for Nuclear Explosion Monitoring

W. A. Peters, A. C. Bakken, A. K. Grimm, T. L. Grimm, N. C. Johnson, M. Mamtimin, F. Y. Odeh, K. A. Shannon, V. N. Starovoitova (Niowave, inc.), S. A. Pozzi, C. Sivels (Univ. Michigan)

Small Modular Reactor as a Part of a District Heating System

Ville Tulkki, Esa Pursiheimo, Tomi J. Lindroos, Ville Sahlberg (VTT)

The Requirement for Variable Electricity from Base-Load Nuclear Power Plants: Role of Heat Storage

Charles Forsberg (MIT)

Assessment of a Nuclear Reactor-Thermal Energy Storage Coupled System

Saeed A. Alameri, Ahmed K. Alkaabi (Khalifa Univ.)

Economic Assessment of Nuclear Hybrid Energy Systems: A Framework Demonstration Case

Aaron S. Epiney, Andrea Alfonsi, P. Talbot, Cristian Rabiti (INL)

Light Water Reactors with Heat Storage and Auxiliary-Combustion Steam Generation to Maximize Electricity and Capacity Payment Revenue

Charles Forsberg (MIT), Robert Varrin (Dominion)

All Energy Forum-I-Panel

All Energy Forum-II-Panel

Viability and Deployment of Small Modular Reactors

Zafar ullah Koreshi (Air Univ.)

Progress in Experimental Development of MSR and FHR Technologies

Jan Uhl

A Survey: The Chemical Compatibility of Silicon Carbide with Molten Fluoride Salts

Jo Jo Lee, Yutai Katoh, Takaaki Koyanagi, Lauren Garrison, Wilna Geringer (ORNL)

A Testing Facility for Advanced Reactor Development and Demonstration

F. Y. Odeh, T. L. Grimm, M. Mamtimin (Niowave, Inc.), V. P. Chellapandi, P. Deng, W. S. Yang (Univ. Michigan), R. Bean, A. J. Jinia (Purdue), S. A. Maloy, K. A. Woloshun (LANL)

Experimental Study Progress on Mock-up Helium Circulator with Dry Gas Seal

Ping Ye, Gang Zhao, Jie Wang (Tsinghua Univ.)

Numerical Simulation of Chronic Moisture Graphite Oxidation for MHTGR

Chengqi Wang, Xiaodong Sun (Univ. Michigan), Richard N. Christensen (Ohio State & Univ. Idaho), Shanbin Shi (Univ. Michigan)

A Novel Approach to Advanced Nanostructured Materials Manufacturing

J. J. Graham (Univ. Calif., Berkeley), K. Sridharan, B. R. Maier, H. Yeom (Univ. Wisconsin, Madison), Peter Hosemann (Univ. Calif., Berkeley)

Thermal Conductivity of Thorium Dioxide with Defects

Jungkyu Park, Eduardo B. Farf

Blade Fracture Accident Analysis of Helium Turbine for HTR-10GT

Xiaoyong Yang (Tsinghua Univ.), Haoran Hao (Shanghai Nucl. Eng. Research Des. Inst.), Jie Wang (Tsinghua Univ.)

Comparative Study of Spent Fuel Storage Design Aspects for HTR-PM and Other Pebble-Bed HTGRs

Bin Wu, Jin-hua Wang, Yan Zhang, Yue Li (Inst. Nucl. and New Energy Technol.)

The Influence of Al Content in Steels and Oxygen Concentration in Liquid LBE on the Corrosion Protection of Structural Steel Candidates for Generation IV FBRs

Miroslav P. Popovic, Yun Yang, Peter Hosemann (Univ. Calif., Berkeley)

Effects of Inventory Control on the Performance of HTR-10GT

Xiaoyong Yang (Tsinghua Univ.), Xiao Lin (China United Gas Turbine Co.), Jie Wang, Youjie Zhang (Tsinghua Univ.)

Essential Elements of a Nuclear Construction Performance Assessment

Kathryn Biegel (Univ. Wisconsin, Madison), Daniel Curtis (MIT), Todd Allen (Univ. Wisconsin, Madison)

Shielding Design of the Cold Neutron Source for the KIPT Neutron Source Facility

Zhaopeng Zhong, Yousry Gohar (ANL)

Integral Experiments to Test the Adequacy of Neutron Cross Sections for Simulation of Well-Logging Tools

John C. Stooksbury, Nolan Hertel (Georgia Tech)

MCNP6.1 Computation of Fluence-to-Ambient Dose Equivalent Conversion Factors for a Steel Cube

S. R. McHale, M. Millett (U.S. Naval Academy), A. W. Decker (U.S. Military Academy)

External Dose Assessment During Dismantling Biological Shield of Kori-Unit 1

Choong Wie Lee, Hyung Jun Kim, Donghyun Lee, Si Hyeong Sung, Min Ji Kim, Hee Reyoung Kim (UNIST)

Detailed SCALE Dose Rate Evaluations for a Consolidated Interim Spent Nuclear Fuel Storage Facility

Georgeta Radulescu, Thomas M. Miller, Kaushik Banerjee, Douglas E. Peplow (ORNL)

Comparing A Posteriori Spatial Error Estimators for the SN Neutron Transport Equation

Nathan H. Hart, Yousry Y. Azmy (NCSU), Jose Ignacio Duo (IMPSA)

Data Assimilation of Nuclear Cross Sections Applied to Neutron Multiplicity Counting Experiments

Alexander Clark, John Mattingly (NCSU)

Testing the Sensitivity of a Neural Based Identification Algorithm to Shielding Levels

P. L. Lagari, S. Weidenbenner, M. Alamaniotis, C. K. Choi, L. H. Tsoukalas (Perdue)

Influence of Detector Orientation on Source Localization Error Using Bayesian Parameter Estimation

Jason Hite, John Mattingly (NCSU)

Accelerator Shielding Design for Active Interrogation Methods Development

Cameron A. Miller, Christopher A. Meert, Alek K. Harvis, Shaun D. Clarke, Sara A. Pozzi (Univ. Michigan)

The Radiation Transport Model for Physical Cryptographic Verification of Nuclear Warheads

Jayson R. Vavrek, Brian S. Henderson, Areg Danagoulian (MIT)

A Theoretical Model for the Angular Discretization Error in the Uncollided Scalar Flux Solution of the Discrete Ordinates Method

Xiaoyu Hu, Yousry Y. Azmy (NCSU)

Neutron Moderation Analysis for a Fusion-Based Neutron Source

Abdullah Weiss, Moiz Butt, Xue Yang (Texas A&M, Kingsville)

Evaluation of Russian Roulette and Particle Splitting Monte Carlo Methods for Space Radiation Transport

Rajarshi Pal Chowdhury, Luke A. Stegeman, Amir A. Bahadori (Kansas State)

A Numerical Approach of Designing the Primary Containment Building of a Pressurized Water Reactor

M. Hossain (Bangladesh Univ. Eng. Technol.), A. H. Khan (Jessore Univ.), M. A. R. Sarkar (Bangladesh Univ. Eng. Technol.)

Application of cosSOURCE Code for PWR Primary Coolant System Source Term Analysis

Wen Song, Yeshuai Sun, Hui Yu, Yixue Chen (State Nuclear Power Software Development Center)

Detector Response Forward Modeling Using Kernel Density Estimator Intermediate Staged Sources

Tanim Islam (LLNL)

Investigation on the Resonance Interference Effect Between Adjacent Fuels

Qian Zhang, Qiang Zhao (Harbin Univ.), Liangzhi Cao (Xi'an Jiaotong Univ.)

Accurate Resonance Calculation of the Fuel Rod with Non-Uniform Temperature Profile

Qian Zhang, Rong Jiang, Qiang Zhao (Harbin Univ.)

Exploring Molten-Salt Reactor Source Terms

Alexander M. Wheeler, Vikram Singh, Laurence F. Miller, Ond?ej Chv

CMM Perturbation Theory and AI Engineering Design Optimization

Albert Gu (SJTU)

Testing and Verification of Multiphysics Tools for Fast-Spectrum MSRs: The CNRS Benchmark

Manuele Aufiero, Pablo Rubiolo (Grenoble Inst. Technol.)

Whole Core Multiphysics Simulations Enabled Through Pin Resolved Transport

Benjamin Collins (ORNL)

An Improved Kaniadakis Doppler Broadening Function

Guilherme Guedes (CEFET), Daniel A. P. Palma (Comiss

Estimation of Subcriticality Using Particle Filter Method

Takuya Ikeda, Toshiki Kimura, Tomohiro Endo, Akio Yamamoto (Nagoya Univ.)

Design Optimization of Additively Manufactured HFIR Control Elements

J. R. Burns, D. Chandler (ORNL), B. Petrovic (Georgia Tech.)

Further Development of Efficient Uncertainty Quantification Techniques for Core Simulation

Dongli Huang, Hany S. Abdel-Khalik (Purdue), Ondrej Chvala, G. Ivan Maldonado (Univ. Tenn.)

Preliminary Simulation Results of VERA Problems 6 and 7 Using NECP-X/SUBSC

Jun Chen, Liangzhi Cao, Xingjian Wen, Zhouyu Liu, Hongchun Wu (Xi'an Jiaotong Univ.)

A Hybrid Subcritical Testbed for Fast Neutron Irradiation of Novel Fuels and Claddings in Fast Reactors

P. Deng, W. S. Yang, V. P. Chellapandi (Univ. Michigan), F. Y. Odeh, M. Mamtimin, T. L. Grimm (Niowave, Inc.)

Development of a Limited Angle Gamma Ray Emission Tomography System for In-Situ Spatially-Resolved Measurement of Fuel Burn Up and Pre-Shutdown Power

Kirk D. Atkinson, Luciano Grana (Defence Academy U.K.)

Quantification of Modeling Approximation Error of Pin-Cell Calculation Using Kriging and Principal Component Analysis

Tomomi Hanai, Akio Yamamoto, Tomohiro Endo (Nagoya Univ.), Kento Yamamoto, Yasunori Ohoka, Hiroaki Nagano (Nuclear Fuel Industries, Ltd.)

Calculation of the Cross Power Spectral Density for Pulse Mode Detectors

A. Talamo, Y. Gohar (ANL), T. Yamamoto, M. Yamanaka, C. H. Pyeon (Kyoto Univ.)

A Mixed-Integer Linear Programming Method for Optimal Orificing in Breed-and-Burn Cores

Chris Keckler, Alper Atamt

A New Stable Finite Element Method for Solving the First-Order Neutron Transport Equation

Liangzhi Cao, Chao Fang, Hongchun Wu, Yunzhao Li (Xi' an Jiaotong Univ.)

Monte Carlo Resonance Calculation for the Method of Characteristics

Hongchun Wu, Qi Zheng, Yunzhao Li, Wei Shen (Xi'an Jiaotong Univ.)

Parallelization of the Pin Resolved Variational Nodal Method

Yongping Wang (Xi'an Jiaotong Univ. & Univ. Michigan), Tengfei Zhang (Shanghai Jiao Tong Univ.), E. E. Lewis (Northwestern), W. S. Yang (Univ. Michigan), M. A. Smith (ANL), Hongchun Wu (Xi'an Jiaotong Univ.)

Analysis of Two-Dimensional Full-Core One-Step Calculation with Bamboo-Lattice

Yunzhao Li, Dongyong Wang, Hongchun Wu, Wei Shen (Xi'an Jiaotong Univ.)

A New Monte Carlo Alpha-Eigenvalue Estimator with Delayed Neutrons

Colin Josey, Forrest B. Brown (LANL)

Generalized Partitioned Matrix Acceleration of Variational Nodal Method

Yongping Wang (Xi'an Jiaotong Univ. & Univ. Michigan), Tengfei Zhang (Shanghai Jiao Tong Univ.), E. E. Lewis (Northwestern), W. S. Yang (Univ. Michigan), M. A. Smith (ANL), Hongchun Wu (Xi'an Jiaotong Univ.)

Temperature Feedback Effect Incorporated in HIRE-Theoretic Multigroup Transport Equations

YuGwon Jo, Nam Zin Cho (KAIST)

Application of the Ratio Correction Fission Matrix Method to a 2-D Four-Assembly Model

Donghao He, William J. Walters (Penn State)

Nuclear Data Sensitivity Analysis in OpenMC Using the GPT-Free Method

Jingang Liang (MIT), Zeyun Wu (Virginia Commonwealth), Hany S. Abdel-Khalik (Purdue)

Application of Multi-Node SPH Factor Generation to PHWR Lattice Homogenization

Thomas A. Ferguson, Eleodor Nichita (Univ. Ontario Inst. Technol.)

Acceleration Methods for Whole Core Reactor Simulations Using VERA

Benjamin Collins, Shane Stimpson (ORNL)

Application of the APEC Method to MOX Fuel Loaded PWR Cores

Woosong Kim, Yonghee Kim (KAIST)

Decay Heat Curve Generation for High Temperature Reactors Using Exponentials, Support Vector Machines and Dynamic Mode Decomposition Within the RAVEN Framework

Andrea Alfonsi, Andrew Hummel, Sonat Sen, Gerhard Strydom, Hans Gougar (INL)

Enhanced Embedded Self-Shielding Method

Qian Zhang, Qiang Zhao (Harbin Univ.), Hongchun Wu (Xi'an Jiaotong Univ.)

Objectives of the NEAMS Workbench

B. T. Rearden, R. A. Lefebvre (ORNL)

NEAMS Workbench 1.0 Beta Status

Robert A. Lefebvre, Adam B. Thompson, Brandon R. Langley, Bradley T. Rearden (ORNL)

MOOSE Integration in the NEAMS Workbench

Robert A. Lefebvre (ORNL), Cody J. Permann (INL), Brandon R. Langley, Bradley T. Rearden (ORNL), Richard C. Martineau (INL)

Integration of the Argonne Reactor Computation Codes into the NEAMS Workbench

Nicolas E. Stauff (ANL), Robert A. Lefebvre, Brandon R. Langley (ORNL), Taek K. Kim (ANL), Bradley T. Rearden (ORNL)

Preliminary Integration of MCNP6 and PROTEUS into the NEAMS Workbench

Kurt A. Dominesey, Matthew D. Eklund, Peter J. Kowal, Wei Ji (RPI)

Integration of the Nek5000 Computational Fluid Dynamics Code to the NEAMS Workbench

Marc-Olivier G. Delchini, Robert A. Lefebvre, W. David Pointer, Bradley T. Rearden (ORNL)

Warthog: At the Intersection of MOOSE and SHARP

Kevin J. Dugan, Shane W. D. Hart (ORNL)

The NEAMS Workbench and Dakota: Providing an Environment for Uncertainty Analyses

Laura Swiler (SNL), Robert Lefebvre, Brandon Langley, Adam Thompson (ORNL)

Application of the Interface Between Dakota and the Argonne Reactor Computation Codes in the NEAMS Workbench

Nicolas E. Stauff* (ANL), Robert A. Lefebvre (ORNL), Laura Swiler (SNL), Taek K. Kim (ANL), Bradley T. Rearden (ORNL)

Providing a Graphical Tool for Modeling Reactor Cores

Patrick O'Leary, Jacob Becker, Robert O'Bara, David Thompson (Kitware, Inc.), Rajeev Jain, Vijay Mahadevan (ANL)

Enhanced Engineering Analyses with Visualization of Geometry and Mesh-Based Data in Fulcrum

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

High Power Density Annular Fuel in a Fast Test Reactor

Bo Feng, Nicolas Stauff (ANL)

Advances in Fast Reactor Design and Concepts-Panel

Core Power Flattening Studies Supporting Narrowing Transient Pulse Widths in TREAT

John D. Bess (INL), Louis M. Dusanter (Ecole Polytechnique), Nicolas E. Woolstenhulme, James R. Parry, Connie M. Hill, Cliff B. Davis (INL)

The Combinational Use of Burnable Poison Pins for 24 Months Cycle PWR

Minjae Lee, Aiman Dandi, Myung Hyun Kim (Kyung Hee Univ.), Soon Ki Kim, Sang Rin Shon (KEPCO)

Online Adversarial Estimation of Reactor Kinetics Parameters

Yeni Li, Elisa Bertino, Hany S. Abdel-Khalik (Purdue)

Neutronic and Fuel Performance Evaluation of Accident Tolerant Fuel Concepts in APR1400 Reactor

Zainab Alnoamani, Saeed A. Alameri (Khalifa Univ.), Mohamed Elsawi (TerraPower)

Application of Fission Matrix Correction Method to TRIGA Reactor Core

Adam Rau, Donghao He, William J. Walters (Penn State)

Measurements of Liquid-Phase Turbulence in Air-Water Two-Phase Flows Using PIV

Yalan Qian (Univ. Michigan & Shanghai Jiao Tong Univ.), Shanbin Shi (Univ. Michigan), Dewei Wang, Yang Liu (Virginia Tech.), Junlian Yin (Shanghai Jiao Tong Univ.), Xiaodong Sun (Univ. Michigan)

Drift-Flux Analysis for Horizontal Air-Water Flow

Ran Kong, Qingzi Zhu, Seungjin Kim, Mamoru Ishii (Purdue)

Drift-Flux Analysis for Downward Air-Water Two-Phase Flow

Qingzi Zhu, Ran Kong, Seungjin Kim, Mamoru Ishii (Purdue)

Characteristic Effects of Pipe Size on Horizontal Two-Phase Flow

Ran Kong, Seungjin Kim (Purdue), Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie (U.S. NRC)

Investigation of Wall Effect on Deformable Bubble Using Interface Tracking Method

Yuqiao Fan (NCSU), Jinyong Feng (MIT), Igor Bolotnov (NCSU)

Development of Evaporation and Condensation Model?Pool Boiling Simulation Using ITM Approach

Mengnan Li, Igor Bolotnov (NCSU)

CFD Study of Subcooled Boiling in a Parallel Plate Assembly of a Research Reactor

Mark Ho (Australian Nuclear Sci. Technol.), Guan Yeoh, Robert Mardus-Hall (Univ. New South Wales), George Braoudakis (Australian Nuclear Sci. Technol.)

Kinetic Precursor Drift Model for Fluid-Fueled Molten Salt Reactors

M. Scott Greenwood, Ben Betzler (ORNL)

Development of MSR Transient Safety Analysis Capability in SAM

Guanheng Zhang, Rui Hu (ANL)

Modeling the Molten Salt Reactor Experiment with the System Analysis Module (SAM)

Adrian M. Leandro (Penn State), Rui Hu, Florent Heidet (ANL), Nicholas R. Brown (Penn State)

Implementation of General Species Transport Capability into VERA-CS for Molten Salt Reactor Analysis

Zachary Taylor (Univ. Tenn.), Robert Salko, Benjamin Collins (ORNL)

Code Comparison of Thermal-Hydraulic Uncertainty Propagation Licensing Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor (TUPLA-FHR) with DAKOTA+RELAP5-3D

R. Romatoski (St. Ambrose Univ.), K. Sun, L. Hu (MIT)

Thermal-Hydraulics of a FLiBe Natural Circulation Flow Loop

Karl Britsch, Kumar Sridharan, Mark Anderson (Univ. Wisconsin, Madison)

Stability Analysis of a Molten FLiBe Natural Circulation Loop Using the Nyquist Criterion

Mohamed Abou Dbai, Raluca O. Scarlat (Univ. Wisconsin, Madison)

FLiBe Radiative Heat Transfer

Will Derdeyn, Mohamed Abou Dbai, Raluca O. Scarlat, Mario Trujillo (Univ. Wisconsin, Madison)

Experimental Studies on Thermal-Hydraulics of FHR Pebble Bed Core

Limin Liu (Xi'an Jiaotong Univ. & Univ. Calif., Berkeley), Dalin Zhang (Xi'an Jiaotong Univ.), Per F. Peterson (Univ. Calif., Berkeley)

Application of the Dynamical System Scaling Methodology

Stephen Heagy, Cesare Frepoli (FPoliSolutions), Jose Reyes (NuScale)

Predictive Capability and Maturity Assessment with Bayesian Network

Linyu Lin, Nam Dinh (NCSU)

Study of Data-Driven Mesh-Model Optimization in System Thermal-Hydraulic Simulation

Han Bao, Nam Dinh (NCSU), Jeffrey Lane (Zachry Nuclear), Robert Youngblood (INL)

Experimental Investigation of Plenum-to-Plenum Natural Circulation Heat Transfer in a Prismatic Very-High-Temperature Reactor

Salman Alshehri (Missouri Univ. Sci. Technol. & King Abdulaziz City Sci. Technol.), Ibrahim A. Said (Missouri Univ. Sci. Technol. & Alexandria Univ.), Muthanna H. Al-Dahhan, Shoaib Usman (Missouri Univ. Sci. Technol.)

Experimental Investigation on Heat Transfer Characteristics with Nonuniform Heat Flux Distribution Under Natural Circulation

Salman M. Alshehri (Missouri Univ. Sci. Technol. & King Abdulaziz Univ. Sci. Technol.), Ibrahim A. Said (Missouri Univ. Sci. Technol. & Alexandria Univ.), Muthanna H. Al-Dahhan, Shoaib Usman (Missouri Univ. Sci. Technol.)

Optimal Working Fluid Charge and Degradation Thresholds for a Natural Circulation Heat Transport Loop

Douglas A. Fynan, Jin Hee Park (KAERI)

Computational Fluid Dynamics Codes for Nuclear Thermal Hydraulics Applications-Panel

Development of a Novel Resistive Heater for Performing Simulated Nuclear Fuel Experiments

Daniel P. LaBrier, Wade R. Marcum (Oregon State), James Nylander (Harris Thermal Transfer Products)

Matched Refractive Index Rod Bundle and Spacer Grid Testing Facility Experiments

A. A. Campagnole dos Santos (Centro de Desenvolvimento da Technologica Nuclear), M. Childs, T. D. Nguyen, Y. Hassan (Texas A&M)

Time-Resolved Particle Image Velocimetry Measurements and Proper Orthogonal Decomposition Analysis of Jet Impingement in a HTGR Upper Plenum

Anas Alwafi (Texas A&M & King Abdulaziz City for Sci. and Technol.), Thien Nguyen, N. K. Anand, Yassin Hassan (Texas A&M)

Time-Resolved Particle Image Velocimetry Measurements in a Low-Aspect Ratio Pebble Bed Reactor

E. Kappes, M. Marciniak, S. King, A. Mills, R. Muyshondt, D. T. Nguyen, Y. A. Hassan, V. Ugaz (Texas A&M)

A New High Pressure Pump Testing Loop

Guillaume P. Mignot, Wade R. Marcum, Sean O'Brien (Oregon State)

On the Performance of the Transient Reactor Test Loop (TRTL)

Daniel P. LaBrier, Wade R. Marcum, Aaron W. Weiss, Guillaume P. Mignot, Emory Brown, Yikuan Yan, Musa Moussaoui, Tsung-Wen Chen (Oregon State)

Drift Flux Model Analysis of Vertical Air-Water Downward Two-Phase Flow in Large Diameter Pipes

M. Yousaf, G. Wang, Z. Dang, M. Ishii (Purdue)

Experimental Validation of Condensation Heat Transfer in PCCS (Passive Containment Cooling System) Heat Exchanger

Byoung-Uhn Bae, Seok Kim, Yu-Sun Park, Hyung-Gil Jun, Kyoung-Ho Kang (KAERI)

Scaling of ADS-4 Depressurization and Long-Term Gravity Injection

Yuquan Li (State Power Investment Corp.), Huajian Chang (Tsinghua Univ.)

Full Scale Experimental Study of Entrainment at ADS-4 Branch of CAP1400

P. Zhang, Y. Q. Li, P. P. Chen, H. J. Chang (State Power Investment Corp. & Tsinghua Univ.)

Oxidation Effect on Flow Boiling CHF of SA508 Under ERVC

Xiang Zhang, Yanfang Xue, Yuquan Li, Huajian Chang (State Nuclear Power Technol. Resaerch Center & Tsinghua Univ.)

Experiment and Numerical Study of Water Film/Air Counter-Current Flow Heat Transfer on a Vertical Plate for Passive Containment Cooling System

Po Hu, Kashuai Du, Xiaojie Yang (Shanghai Jiao Tong Univ.)

Direct Temperature Measurement Method of Nuclear Reactor Graphite Core

Cheng Ren, Zhen Zhang, Xingtuan Yang (Tsinghua Univ.)

Experimental Study on the Molten Pool Oxide-Layer Characteristics

Daogui Tian, Lian Chen, Kun Han, Tao Li, Jie Pei, Bin Jiang, Huajian Chang (State Nuclear Power Technol. Center)

Interfacial Area Transport in Horizontal Bubbly Flow

Ran Kong, Seungjin Kim (Purdue), Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie (U.S. NRC)

Implicit Second-Order Scheme for Steady-State Thermal-Hydraulic Simulations

Guojun Hu, Tomasz Kozlowski (Univ. Illinois, Urbana-Champaign)

Adjoint Sensitivity Analysis of the Two-Phase Two-Fluid Model

Guojun Hu, Tomasz Kozlowski (Univ. Illinois, Urbana-Champaign)

Validation Hierarchy for Waste Vitrification Models

D. P. Guillen, A. W. Abboud (INL), R. Pokorny (Univ. Chemistry Technol. Prague), W. C. Eaton, D. Dixon (PNNL), K. Fox (SRNL), A. A. Kruger (U.S. DOE)

Thermal Evaluations for Tank Cesium Removal System

Si Young Lee (SRNL), Amy L. Lloyd (Mercer Univ.)

Stabilized Finite Element Formulation for Thermally-Driven Porous Media Flows in Pronghorn

Ling Zou, John W. Peterson (INL), April J. Novak (Univ. Calif., Berkeley), Richard C. Martineau, Hans D. Gougar (INL)

Low Mach Number Acoustics in Nuclear Piping Systems

Alexander Boschitsch, Pavel Danilov, Alan Bilanin (Continuum Dynamics, Inc.)

Numerical

Cen Wei, Bao-wen Yang, Bin Han (Jiaotong Univ.)

Rod Bundle Mixing Test and Subchannel Analysis with Modified Turbulent Mixing Model

Aiguo Liu, Bao-Wen Yang, Xianlin Zhu (Xi'an Jiaotong Univ.)

One-Dimensional Thermal Hydraulic Analysis of a Light Water Reactor Fuel Channel

Jerald C. Daniel, Kurshad Muftuoglu (Univ. Pitt.)

Effect of Twisted Tapes on the Natural Circulation, Heat Transfer, and Pressure Drop Enhancements

Salman Alzahrani (King Abdulaziz City Sci. Technol., & Missouri Univ. Sci. Technol.), Shoaib Usman (Missouri Univ. Sci. Technol.)

Severe Accident Mitigation Strategy of IVR-ERVC for Small Integral Reactor

Rae-Joon Park, Dong Gun Song (KAERI)

Lagrangian CFD Analyses for Use in DOE M 441.1-1 Calculations

S. M. McGuffie (Porter McGuffie, Inc.), M. Alsharif, Y. He (Consolidated Nuclear Secutiry, LLC.)

A Computer Code for Thermal-Hydraulic Analysis of Steam Generator with Axial Preheater/Economizer

Ge Wu, Gening He, Haisong Wang (Nucl. Power Inst. China)

Preliminary Assessment of CHF Model Based on Dry Patch and Heat Dissipation Concepts Using Vertical Heaters

Dong Hoon Kam, Yong Hoon Jeong (KAIST)

Prediction of Condensation Heat Transfer for Steam with a Non-Condensable Gas of TASS/SMR Code at High-Pressure Conditions

Y. J. Chung, H. J. Kim, H. S. Kim, S. H. Kim, K. H. Bae (KAERI)

Study on Rod Bundles CHF Prediction by Liquid Sublayer Dryout Model

Dawei Zhao (Nuclear Power Inst. China), Juliana Pacheco Duarte, Michael L. Corradini (Univ. Wisconsin, Madison)

Towards Low Prandtl Number Investigations with Direct Numerical Simulation in Fuel Bundles

Jonathan K. Lai (Texas A&M), Elia Merzari (ANL), Yassin A. Hassan (Texas A&M)

Large Eddy Simulations on Turbulent Flow of Twin Parallel Jets

Han Li, N. K. Anand, Yassin A. Hassan (Texas A&M)

Simulation of Flow Across a Spacer Grid with RANS and LES Turbulence Models

Giacomo Busco, Yassin A. Hassan (Texas A&M)

Flow Development with LES for Cold Leg Mixing Benchmark

Jonathan K. Lai (Texas A&M), Elia Merzari (ANL), Yassin A. Hassan (Texas A&M)

CFD-DEM Analysis of Heated Pebble Bed Geometry

Robert Mardus-Hall (Univ. New South Wales), Mark Ho (ANSTO), Guan Yeoh (Univ. New South Wales, ANSTO)

An Uncertainty Quantification of the Computational Fluid Dynamics Solution to the Modeling of the Contact Point in a Wire-Wrapped Fuel Assembly

Marc-Olivier G. Delchini (ORNL), Laura P. Swiler (SNL), Emilian P. Popov, William D. Pointer (ORNL)

Advanced Computational Accident Scenario Modeling for Safety Margin Economic Analysis

Thomas Riley, Andrew Klein (Oregon State)

Accident Tolerant Fuels (ATF) Coating and Cladding Thermal Hydraulic Properties Evaluation by MELCOR YU 1.8.6: Benchmark for SURRY Short Term Station Black Out

Jun Wang, Michael L. Corradini, Hangjin Jo (Univ. Wisconsin, Madison)

CFD-Assisted Analytical Work of Pressure Vessel Rupture Size Enlargement During Severe Accidents

Mun Won Song, Hee Cheon No (KAIST)

A Model for Growth and Fracture of Crust Before Water Ingression

Dong Yeol Yeo, Hee Cheon No (KAIST)

Investigations on the Hydrogen Risk in the Filtered Containment Venting System Using MELCOR

Hoe-Yeol Kim, Dong-Wook Jerng, Eun-Hye Lee (Chung-Ang Univ.)

Comparative Analysis of Conventional and Compact Heat Exchangers for Next Generation Nuclear Reactors

Amey Shigrekar (Univ. Idaho), Piyush Sabharwall (INL), Richard Christensen (Univ. Idaho)

Influence of Dissolved Impurities on the Coolability of Nuclear Fuel Rods

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

A Dryout Model of CRUD

Dong Yeol Yeo, Hee Cheon No (KAIST)

Multiple Branches Coupling Property and Design of PRHRs

Zhang Zhuohua, Ran Xu, Li Feng, Xian Lin, Zhou Ke (Nuclear Power Inst. China)

Buoyancy and Thermal Expansion Acceleration Effects of Supercritical CO2 Flowing in a Helically Coiled Tube

Xiao-Rui Huang, Zhen Zhang, Xing-Tuan Yang (Tsinghua Univ.)

Meet with ANS Staff-Panel

Students for Nuclear-Telling your Nuclear Story-Panel

Water Technologies and Nuclear Power-Panel

Expediting the Licensing and Deployment of Advanced Reactors-Panel

Load Following Attributes for Nuclear-Panel

Nuclear Advocacy-Panel

NFSM 2018 Plenary

SiC-SiC Composite Cladding Development for Accident Tolerant Fuel

C. P. Deck, H. E. Khalifa, K. S. Shapovalov, S. Gonderman, G. M. Jacobsen, J. Sheeder, G. Vasudevamurthy, ?C. Shih, E. Song, S. Oswald, R. Haefelfinger, C. Bacalski, J. Zhang (General Atomics), R. J. Jacko (Westinghouse), J. Gazza, C. A. Back (General Atomics)

Sensitization Resistance of FeCrAl Alloys for Welded Fuel Cladding

Vipul K. Gupta, R. J. Blair, Raul B. Rebak (GE)

Update on Westinghouse EnCore

R. Oelrich, P. Xu, E. Lahoda (Westinghouse), C. Deck (General Atomics)

Development of Novel Nuclear Fuel Materials for Light Water Reactors

A. T. Nelson

Uranium Silicide and Uranium Silicide-Nitride Fuels: ?Assessing Phase Behavior for Fabrication and In-Reactor Behavior

Tashiema L. Wilson, Denise L. Adorno, Vancho Kocevski, Emily E. Moore (Univ. South Carolina), Joshua T. White (LANL), Elizabeth Sooby Wood (Univ. Texas, San Antonia), Andrew T. Nelson (LANL), Peng Xu (Westinghouse), Simon C. Middleburgh (Bangor Univ.), Jacob W. McMurray (ORNL), Theodore M. Besmann (Univ. South Carolina)

Developments in Fuel Modeling within the NEAMS Program

Christopher R. Stanek (LANL)

Multiscale Modeling of Fission Gas Bubble Evolution in UO2 Under Nominal Operating Conditions

B. D. Wirth (Univ. Tenn. & ORNL), A. D. Andersson (LANL), S. Blondel (Univ. Tenn.), G. Pastore (INL), R. J. Kurtz, W. Setyawan (PNNL)

Atomistic Simulations of Point Defect Behavior in Nuclear Fuels

David Andersson, Michael Cooper, Topher Matthews, Romain Perriot, Xiang-Yang Liu, Chris Stanek (LANL)

BISON: A Multidimensional Fuel Performance Code

Giovanni Pastore, Benjamin Spencer, Richard Williamson, Jason Hales (INL)

Extending the Capability of Nuclear Plant Systems Analysis with Advanced Tightly-Coupled Nuclear Fuels Performance

Richard Martineau, David Andrs, Joshua Hansel, Cody Permann, Derek Gaston, Steve Novascone (INL), Matthew Bernard (U.S. NRC), Russel Johns (LANL), Rui Hu, Elia Merzari (ANL), James Wolf, Hongbin Zhang, Ronaldo Szilard (INL)

Introduction of the Meso-Scale Fuel Performance Modeling Code MARMOT

Yongfeng Zhang, Daniel Schwen (INL), David Andersson (LANL), Michael Tonks (Univ. Florida), Stephen Novascone (INL), Karim Ahmed (Texas A&M)

Calibration of Zr Redistribution Models for Metallic Fuel in BISON

Christopher Matthews, Garrison Stevens, Cetin Unal (LANL)

Machine Learning Applications and Opportunities in Nuclear Materials

Dane Morgan, Wei Li, Tam Mayeshiba, Henry Wu, Benjamin Afflerbach (Univ. Wisconsin, Madison), Peter Wells, G. Robert Odette (Univ. Calif. Santa Barbara), Kevin Field (ORNL)

Entrepreneurial Nuclear and the Associated Challenges for Materials Development

T. R. Allen (Univ. Wisconsin, Madison)

Modeling of Structural Graphite for Pebble Bed HTGR Cores

Paul Kirchman, Pete Pappano (X-Energy)

HT9 Material Development for the TWR Core

Greg Vetterick, Cheng Xu (TerraPower)

Technology Development in Fuels and Materials for the Fluoride-Salt Cooled High Temperature Reactor

Micah Hackett, Alan Kruizenga, Michael Hanson (Kairos Power), Sam Sham (ANL), George Young (Dominion)

Designing for Radiation Tolerance in FeCrAl Alloys

Kevin G. Field (ORNL), Samuel A. Briggs (SNL), Dalong Zhang, Kenneth C. Littrell, Yukinori Yamamoto (ORNL)

Mechanical Response of SiC-SiC Composite Cladding at Accident Relevant Temperatures

Kirill Shapovalov, George M. Jacobsen, Christian P. Deck (General Atomics)

Hydrothermal Corrosion of Candidate Coatings on Silicon Carbide

Stephen S. Raiman, Peter Doyle (ORNL)

Nitrogen Effects on Irradiated Ferritic/Martensitic Steel

Ben Eftink, Matthew Chancey, Di Chen, Yongqiang Wang, Stuart Maloy (LANL)

Investigating Pd as a Potential Fuel Additive to Control FCCI

Michael T. Benson, Lingfeng He, James A. King, Robert D. Mariani (INL)

Fabrication of Graphite?LEU Fuel for TREAT Reactor Conversion

Dustin R. Cummins, Erik P. Luther (LANL), Ben D. Coryell (INL), Timothy Baker (LANL), Douglas E. Burns (INL)

Fabrication and Characterization of U-Zr Foils for the DISECT Project

Walter J. Williams (Purduue & INL), Maria A. Okuniewski (Purdue), Laura Sudderth, Daniel Wachs (INL), Sven Van den Berghe (SCK-CEN)

First-Principles Study of the Fracture Toughness of Transition Metal Nitride Thin Films for U-Mo/Al Dispersion Fuel

Zhi-Gang Mei, Abdellatif M. Yacout (ANL)

Effect of a Raw Material Powder on Sintered CeO2 Pellets by 28 GHz Microwave Irradiation

Masatoshi Akashi, Taku Matsumoto, Masato Kato (JAEA)

Characterization of U-Zr Alloy System Fuel Slugs Prepared with Recycled Metallic Fuel Scraps

Ki-Hwan Kim (KAERI), Seong-Jun Ha (Chungnam Univ.), Jeong-Yong Park, Seok-Jin Oh, Sung-Ho Kim (KAERI)

Thermophysical Properties of Select Uranium-Palladium Metallic Fuel Alloys

Scott Middlemas, Cynthia Papesch, Craig Marshall (INL)

Processing of Enhanced UO2 Fuel Starting from a Sol-Gel Feedstock

Sarah Finkeldei, Jim Kiggans, Rodney Hunt, Kurt Terrani (ORNL)

Microstructural Degradation of U3Si2 and Fission Product Silicides Exposed to H2O Containing Atmospheres

Elizabeth Sooby Wood, Geronimo Robles (Univ. Texas, San Antonio), Joshua T. White, Christopher J. Grote, Andrew T. Nelson (LANL)

Thermophysical Properties Evaluation of U-x wt%Pu-20 wt%Zr Metallic Fuel, Where x = 30, 36.5, and 55

Cynthia A. Adkins, Scott Middlemas (INL)

Assessment of Radiation Damage and Microstructural Changes in Neutron Irradiated U-10Zr Fuels with High Energy X-Rays

Jonova Thomas, Sri Tapaswi Nori, Alejandro Figueroa, Ran Ren, Maria A. Okuniewski (Purdue), Peter Kenesei, Jun Sang-Park, Jon Almer, (ANL) Jason M. Harp (INL)

Synthesis, Sintering, and Thermophysical Properties of Thorium Mononitride

Stephen S. Parker (Univ. Calif., Berkeley & ORNL), Joshua T. White (ORNL), Peter Hosemann (Univ. Calif., Berkeley), Andrew T. Nelson (ORNL)

Axial and Hoop Creep Mechanisms of ZIRLO

Micah G. Tillman, N. Kumar, K. L. Murty (NCSU)

Microstructural Characterization of ECAP Processed Grade 91 During In-Situ Annealing

Ryan Carnahan, Malwina Wilding, Cheng Sun, Mary Lou Dunzik-Gougar, Thomas M. Lillo (INL)

Hydrogen Precipitation Kinetics Measurement in Zircaloy-4 Using Synchrotron Irradiation X-Ray Diffraction

Evrard Lacroix, Arthur T. Motta (Penn State)

Electronic Structure Characterization of Oxide Films on Zirconium Alloy in High Temperature Water

Taeho Kim, Seunghyun Kim, Yunju Lee, Junhyuk Ham, Ji Hyun Kim (UNIST)

Simulating Hydrogen Solvus in Zirconium by Hyrax: A Mesoscale Phase-Field Code

Jun-Li Lin, Brent Heuser (Univ.Illinois, Urbana-Champaign)

Enhanced High-Temperature Performance of a Zirconium Alloy Cladding by High-Temperature Preformed Oxide

Cheol Min Lee (UNIST), Yong-Kyoon Mok (KEPCO), Dong-Seong Sohn (UNIST)

Solid Mechanics Behavior of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, FeCrAl and Surface-Coated Claddings

Wei Zhou, Wenzhong Zhou (Univ. Hong Kong)

OFRAC: An Advanced Nanostructured Ferritic Alloy Fuel Cladding for Fast Reactors

Caleb P. Massey (Univ. Tenn.), David T. Hoelzer, Philip D. Edmondson (ORNL), Rachel L. Seibert (Illinois Inst. Technol.), Anoop Kini, Baptiste Gault (Max-Planck), Kurt A. Terrani (ORNL), Steven J. Zinkle (ORNL & Univ. Tenn.)

Molecular Dynamics Simulations of Gap Thermal Conductance

Lin Zhang, Heng Ban (Univ. Pitt.)

Multiphysics Simulation of Thermal Striping for Determining Creep-Fatigue Life

M. C. Messner, Y. Yu (ANL)

Nickel-Based Structural Material MONICR for Molten Salt Reactors Applications

Martina Koukolikova, Peter Slama, Pavel Podany, Jan Cerny (COMTES FHT)

Recrystallization Behaviour of Nickel-Based Superalloys for Molten Salt Reactors

Pavel Podany, Martina Koukolikova, Peter Slama, Petr Motycka (COMTES FHT)

High Temperature Creep Properties of Alloy 709

A. S. Alomari, N. Kumar, K. L. Murty (NCSU)

Characterization of Nuclear Materials with Neutron Diffraction and Neutron Imaging

Sven C. Vogel, Donald W. Brown, Adrian S. Losko, Tarik A. Saleh (LANL)

Influence of Heat Treatment on the Microstructure and Mechanical Properties of Alloy 825 at Cryogenic Temperatures

Jan Sas, Klaus-Peter Weiss (KIT), Pavel Podany (COMTES FHT)

An Overview of NSUF Facilities at Los Alamos National Laboratory

Tarik A. Saleh, Thomas J. Venhaus, Donald W. Brown, Sven C. Vogel (LANL)

Mitigating Stress Corrosion Cracking and Irradiation Defects in ODS Austenitic Alloys by Laser Shock Peening

Xueliang Yan, Yongfeng Lu, Michael Nastasi, Bai Cui (Univ. Nebraska)

Corrosion Resistant Materials Testing and Compatibility Studies in High Temperature Lead Bismuth Eutectic

Stuart Maloy, Keith Woloshun (LANL), Mayir Mamtimin, John Diemer, Terry Grimm, Faisal Odeh, Tim Shade (Niowave)

Tribological Behavior of Structural Materials at Elevated Temperatures and in Impure Helium Environments for High-Temperature Gas-Cooled Reactor Applications

Valentin Pauly, Carter Tesch, Joseph Kern, David Grierson, Dileep Singh, Oyelayo Ajayi, Kumar Sridharan (Univ. Wisconsin, Madison)

Electrochemistry of FeCrAl Fuel Cladding in High Temperature Water.

Timothy B. Jurewicz, Raul B. Rebak (GE)

Investigation of Materials Corrosion in Molten Fluoride Salts

C. Falconer, W. H. Doniger (Univ. Wisconsin, Madison), G. Zheng (Univ. Wisconsin, Madison & MIT), R. Scarlat, K. Sridharan, A. Couet (Univ. Wisconsin, Madison)

Design and Development of CANDU Ex-Service Garter Spring Irradiation Experiments in the HFIR

Richard H. Howard, Ryan C. Gallagher (ORNL), Andrew Buyer (CNL)

Enhanced Plasticity in 33 dpa Neutron Irradiated 304SS with 2-3.7% Swelling

H. Vo (Univ. Calif., Berkeley), S. Teysseyre (INL), P. Hosemann (Univ. Calif., Berkeley)

Accelerated Irradiation Testing of Miniature Fuel Specimens

Christian M. Petrie, Joseph Burns, Robert Morris, Kurt Terrani (ORNL)

Radiation-Induced Microstructure Evolution and Hardening of Austenitic Alloy 709

Xiang Liu (Univ. Illinois, Urbana-Champaign), Jonathan Gigax, Lin Shao, Frank A. Garner (Texas A&M), James F. Stubbins (Univ. Illinois, Urbana-Champaign & Kyushu Univ.)

Evaluation of Irradiation-Induced Strain in SiC Tubes by a Combination of Experiment and Simulation

Takaaki Koyanagi, Yutai Katoh, Gyanender Singh, Xunxiang Hu, Christian M. Petrie, Kurt Terrani (ORNL)

Diffusion of Fissile Inventory in AGR-1 TRISO Fuel Particles as a Function of Temperature and Silver Retention

Rachel L. Seibert (Illinois Inst. Technol.), Tyler J. Gerczak, Kurt A. Terrani, John D. Hunn, Fred Montgomery, Charles Baldwin (ORNL), Jeff Terry (Illinois Inst. Technol.)

Nano-Crystallization in UO2 Irradiated by High-Energy Heavy Ions

Yinbin Miao (ANL), Tiankai Yao, Jie Lian (RPI), Shaofei Zhu, Sumit Bhattacharya, Aaron Oaks, Abdellatif M. Yacout, Kun Mo (ANL)

Simulated Effective Thermal Conductivity of U3Si2 Fuels with Irradiated Gas Bubbles

Linyun Liang, Zhi-Gang Mei, Yinbin Miao (ANL), Larry K. Aagesen (INL), Abdellatif M. Yacout (ANL)

Modelling of Uranium Dioxide Oxidation in Air Condition

Hyounggyu Park, Kwangheon Park (Kyunghee Univ.)

Phase Field Simulation of Sintering of UO2 Nuclear Fuel

Ian Greenquist (Penn State), Michael Tonks (Univ. Florida), Yongfeng Zhang (INL)

Neutronic Analysis of Fuel Out Zone Effects for USHPRR Program U-10Mo, Mini-Plate-1 Irradiation at the Advanced Test Reactor

Margaret A. Marshall (INL)

Role of Compression Metallization in UO2 Fission-Product Energy Cascade Track: Multiscale Electron-Phonon Analyses

Woong-Kee Kim (Seoul Univ. & Univ. Michigan), Corey Melnick (Univ. Michigan), Ji Hoon Shim, Massoud Kaviany (Univ. Michigan & Pohang Univ.)

Investigation of Interfaces in Gamma U-Mo

Benjamin Beeler, Yongfeng Zhang, Yipeng Gao (INL)

As-Run Neutronics Analysis for AFIP-6 Mk II Irradiations in ATR for the USHPRR Program

Margaret A. Marshall (INL)

Progress in Coupling of Thermodynamics, Fluid Dynamics, and Isotopics in Molten Salt Reactor Multi-Physics Simulations

B. W. N. Fitzpatrick, M. H. A. Piro (Univ. Ontario Inst. Technol.), B. Collins (ORNL)

Microstructure-Level Modeling of Triple-Junction Fission Gas Bubble Percolation

Larry Aagesen, Daniel Schwen, Yongfeng Zhang (INL)

Evaluation of Precipitation Thermodynamics in MAMBA-3D

Jason T. Rizk, Brian D. Wirth (Univ. Tenn.)

Fuel Performance Analysis of Iron-Chrome-Aluminum Cladding Under Simulated Loss-of-Coolant Conditions

R. T. Sweet (Univ. Tenn), K. A. Terrani, (ORNL) Brian D. Wirth (Univ. Tenn. & ORNL)

Radionuclide Release Modeling from TRISO Based FCM Fuel

Daniel Schappel (Univ. Tenn.), Kurt A. Terrani, Jeffery Powers, Lance Snead (ORNL), Brian D. Wirth (Univ. Tenn. & ORNL)

Design of a Fission Gas Release Measurement System at the PULSTAR Reactor

M. Liu, A. I. Hawari (NCSU)

Physics-Based Computational Modeling of ?-U Thermal Conductivity

Shuxiang Zhou, Ryan Jacob (Univ. Wisconsin, Madison), Eric Tea, Celine Hin (Virginia Tech), Dane Morgan (Univ. Wisconsin, Madison)

Reactivity-Initiated Accident Experimental Benchmarks for the BISON Fuel Performance Code

C. Folsom (Utah State), R. Williamson, G. Pastore (INL), H. Ban (Univ. Pitt)

Using BISON to Design a PCMI Validation Experiment

A. Casagranda, B. W. Spencer, G. Pastore, S. R. Novascone, J. D. Hales, R. L. Williamson, R. C. Martineau (INL)

Engineering Analysis of Reactor Pressure Vessels with Grizzly

Benjamin W. Spencer, William M. Hoffman, Wen Jiang (INL)

Microstructural Evolution of 3C-SiC Exposed to Simultaneous Neutron Irradiation and Helium Implantation

Xunxiang Hu, Takaaki Koyanagi (ORNL), Jiangtao Zhao (Lanzhou Univ.), Takuya Yamamoto (Univ. Calif., Santa Barbara), Yutai Katoh (ORNL)

Characterization of Dislocation Loops and ?? Precipitates in Neutron-Irradiated FeCrAl Weldments

D. Zhang (ORNL), S. A. Briggs (SNL), Y. Yamamoto, R. H. Howard, M. N. Gussev, K. G. Field (ORNL)

Point Defects in Uranium Mono-Nitride: First-Principles Calculations

Behieh M. Elahi, Iyad I. Al-Qasir (Univ. Sharjah)

Microstructural Modifications in U3Si2 Implanted by High-Energy Xe Ions at LWR Temperatures

Yinbin Miao (ANL), Jason Harp (INL), Kun Mo, Shaofei Zhu, Abdellatif M. Yacout (INL)

Fully Ceramic Microencapsulated Fuel in Prismatic High Temperature Gas-Cooled Reactors-Impact on Control Rod Worth and Temperature Distribution in the Core

Cihang Lu, Nicholas R. Brown (Penn State)

Evaluating Accident Tolerant Fuel Concepts in Light Water Reactors Using CASL CTF

Jacob P. Gorton, Nicholas R. Brown (Penn State), Kurt A. Terrani (ORNL), Amir F. Ali, Youho Lee (Univ. New Mexico)

Thermal Neutron Scattering Cross Sections of Molybdenum Isotopes

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

A Proposed Start-Up Fuel for the Versatile Test Reactor

Douglas C. Crawford, Steven L. Hayes (INL), Jeffery J. Powers (ORNL)

New Capabilities for In-Pile Separate Effects Tests in TREAT

N. Woolstenhulme, C. Baker, J. Bess, D. Chapman, D. Dempsey, C. Hill, C. Jensen, S. Snow (INL)

New Generation of Transient Testing for SFR Fuels in TREAT

Colby Jensen, Daniel Wachs, Nicolas Woolstenhulme (INL)

Advanced Manufacturing and Materials to Enable Advanced Nuclear Energy

Kurt A. Terrani (ORNL)

Cold Spray Coatings for Accident Tolerant Zr-Alloy Cladding in Light Water Reactors

Hwasung Yeom, Benjamin Maier, Greg Johnson, Tyler Dabney, Mia Lenling, Payton Scallon (Univ. Wisconsin, Madison), Javier Romero, Jorie Walters, Peng Xu, Hemant Shah (Westinghouse), Kumar Sridharan (Univ. Wisconsin, Madison)

Recent Development in SiC Composite Technologies for Nuclear Energy Applications

Yutai Katoh (ORNL)

Investigation of High-Entropy Alloys Compositions for Radiation Damage Applications

Calvin Parkin, Michael Moorehead, Zefeng Yu, Kumar Sridharan, Adrien Couet (Univ. Wisconsin, Madison), Alfred Ludwig, Alan Savan (Ruhr Univ., Bochum), Chuan Zhang (CompuTherm)

History and Outlook of ODS/NFA Ferritic Alloys for Nuclear Applications

D. T. Hoelzer (ORNL)

Fundamental Aspects of Radiation Effects in Materials

S. J. Zinkle (Univ. Tenn. & ORNL)

Current Status of Postirradiation Examination of the AFC Metallic Fuel

Jason M. Harp, Luca Capriotti, Fabiola Cappia, Steven L. Hayes (INL)

Multi-Scale Analysis of Failed Safety-Tested UO2 Particles from the AGR-2 Fuel Irradiation Experiment

Tyler J. Gerczak, John D. Hunn, Grant Helmreich, Fred Montgomery, Robert N. Morris (ORNL), Rachel L. Seibert (Illinois Inst. Technol.), John A. Dyer, Brian D. Eckhart, Darren J. Skitt (ORNL)

Accident Tolerant Fuels (ATF-1) Irradiation Tests: Overview of the Ongoing Post-Irradiation Examinations

Jason M. Harp, Fabiola Cappia (INL)

Studies on Used Nuclear Fuel Management and Extended Storage at JRC

V. V. Rondinella, T. A. G. Wiss, D. Papaioannou, R. Nasyrow, D. Wegen, S. Bremier (European Commission), F. Cappia (INL), E. Vlassopoulos (EPFL)

Assessing the Effects of Irradiation on Reactor Cavity Concrete

Thomas M. Rosseel, Alain B. Giorla, Maxim N. Gussev, Gerald E. Jellison, Jr., Yann Le Pape, Igor Remec, Chinthatka Silva, Elena Tajuelo Rodriguez, Stephanie M. Curlin, Luis F. Mora (ORNL)

State of Electrical Cable Aging in U.S. Nuclear Power Plants

Leonard S. Fifield (PNNL & Washington State)

Advantages of SEM-EBSD In-Situ Mechanical Testing for Investigating Radiation Effects on Materials

M. N. Gussev, K. G. Field, K. J. Leonard (ORNL)

Mechanical Properties of Irradiated Miniature Nuclear Fuel Related Materials

Mehdi Balooch (Univ. Calif., Berkeley & ORNL), Kurt A. Terrani (ORNL)

High-Resolution Neutron Imaging: Investigating Anisotropic Hydride Structure in Zircaloy-4 Nuclear Fuel Cladding

Jun-Li Lin, Weicheng Zhong (Univ. Illinois, Urbana-Champaign), Hassina Z. Bilheux (ORNL), Brent J. Heuser (Univ. Illinois, Urbana-Champaign)

Modeling and Simulation of Redistribution of Oxygen-to-Metal Ratio in MOX

Shun Hirooka, Masato Kato, Masashi Watanabe (JAEA)

Analysis Techniques for Large Datasets from the National Synchrotron Light Source-II

Lynne E. Ecker, David J. Sprouster (BNL), John Rodman (Syracuse), Shinjae Yoo (BNL)

Overview of the U.S. Nuclear Science User Facilities

J. Rory Kennedy (INL)

In Situ Dual-Beam Ion Irradiation with Transmission Electron Microscopy

Meimei Li, Peter M. Baldo, Marquis A. Kirk, Edward A. Ryan, Jing Hu (ANL)

Understanding Complex Environmental Effects in Nuclear Reactor Relevant Materials Through In-Situ Transmission Electron Microscopy Ion Irradiation

C. M. Barr (SNL), A. Aitkaliyeva (Univ. Florida), K. Hattar (SNL)

The BR2 Reactor as NSUF Affiliate Infrastructure

Steven Van Dyck, Sven Van den Berghe (SCK CEN)

In Situ TEM Clamped Beam Fracture in Fe-9Cr ODS

K. H. Yano, J. P. Wharry (Purdue)

Wigner Energy in SiC and Implications to LWR Design

Lance L. Snead, Koroush Shirvan (MIT)

Micro-Cantilever Testing of Environmental Barrier Coatings on CVD SiC

Joseph Kabel, Peter Hosemann (Univ. Calif., Berkeley), Takaaki Koyonagi, Yutai Katoh (ORNL)

Assessing the Effects of Gamma Irradiation in Concrete

Elena Tajuelo Rodriguez (ORNL), William A. Hunnicutt (Univ. Illinois, Urbana-Champaign), Paramita Mondal (Univ. Illinois, Urbana-Champaign & Univ. Delaware), Yann Le Pape (ORNL)

In-Situ Synchrotron X-Ray Scattering Study on the Tensile Properties? of Neutron Irradiated Ferritic/Martensitic Alloys

Hoon Lee, Xiang Liu, Kuan-Che Lan, Huan Yan (Univ. Illinois, Urbana-Champaign), Meimei Li, Xuan Zhang, Chi Xu, Jun-Sang Park, Jonathan Almer (ANL), James F. Stubbins (Univ. Illinois, Urbana-Champaign & Kyushu Univ.)