Annual Meeting 2016 / Volume 114

Full Issue

Opening Plenary: Nuclear Power: Leading the Supply of Clean, Carbon Free Energy

ANS President's Special Session

TPC Special Session: Developing a Policy for Used Nuclear Fuel that Will Encourage an Expansion of Nuclear Energy as a Leading Supply of Clean Carbon Free Energy

General Chair's Session: Improving the Competitiveness of the Existing U.S. Commercial Nuclear Fleet-Sustaining a National Asset

Accelerator Applications: General

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

Ross F. Radel, Evan Sengbusch, Greg Piefer (Phoenix Nuclear Labs)

Control and Service Life Extension of Accelerator's Anode Voltage Regulator

Robby Christian, Hyun Gook Kang (KAIST)

⁹⁹Mo Production at KIPT Neutron Source Facility

A. Talamo, Y. Gohar (ANL)

Aerospace Nuclear Science and Technology: General-Paper/Panel

Preliminary Neutronic, Thermal and Mechanical Design for Pu-238 Advanced Test Reactor Targets

Jorge Navarro, Craig S. Biebel, Paul E. Murray, Carla C. Dwight (INL)

Role of Core Exit Axial Reflectors for NTP Full Submersion Criticality Accident Mitigation

Paolo F. Venneri, Yonghee Kim (KAIST)

Radiation Transport Applications in Medicine

Analytical Stopping Power and Range Parameterization for Therapeutic Energy Intervals

William P. Donahue, Wayne D. Newhauser (Louisiana State Univ), James F. Ziegler (United States Naval Academy)

Comparison of Proton Energy Deposition from Monte Carlo Simulations and Measurement Results

H. Chen, Z. Xia, L. Derenchuk (ProNova Solutions, LLC), N. Schreuder (Provision Center for Proton Therapy), M. Hansen, R. Moore, Z. Nevitt, J. Volk (ProNova Solutions, LLC)

Broadly Applicable Dose Model for Radiotherapy Beams from 6-25 MV

Christopher Schneider, Wayne D. Newhauser (Louisiana State Univ)

Investigation of the Attila Deterministic Solver for Out-of-Field Organ Dose Calculations for Radiotherapy Patients

Matthew M. Mille (National Cancer Inst, NIH), Choonsik Lee (National Cancer Inst)

The Current State of Radiation Dosimetry in Radionuclide Therapy

Bryan P. Bednarz, Abigail E. Besemer, Ian R. Marsh (Univ of Wisconsin, Madison)

iOS Heartrate Monitor

Abdullah Weiss, Raymond Ayala, Samantha-Lee Villarreal, Xue Yang (Texas A&M Univ)

Focus on Communications: Communication, the Challenges Facing Today's Operating Fleet-Panel

Focus on Communications: Creating New Nuclear Conversations-Panel

Education, Training, and Workforce Development: General

Enhancement of Nuclear Engineering Technology Degree with a Web Based PWR Simulator

Michael C. Johnson, Jane Weyers, Scott Dolan (Excelsior Coll)

Ensuring Workforce Readiness for the Energy Industry through 3D Simulations

Michael C. Johnson, Randy Holt, Scott Dolan (Excelsior Coll)

Development of a Course in Gamma-Ray Spectrometry

S. Landsberger, M. Yoho, E. Zumalt, M. Pitsch (Univ of Texas, Austin)

"Fission", A Board Game for Social Awareness of Nuclear Power

Akansha Kumar (Texas A&M), Kevin J. Schillo (Univ of Alabama, Huntsville)

Tritium Management in the Nuclear Fuel Cycle

Tritium Content in and Release from Pressurized-Water-Reactor Fuel Cladding

Sharon Robinson, Marc Chattin, Joseph M. Giaquinto, Robert T. Jubin (ORNL)

Tritium Distribution and Capture Requirements for UNF Reprocessing

Robert T. Jubin, Barry B. Spencer (ORNL)

Hydrogen Isotope Separation from Aqueous Streams using Zeolite Membranes

Yeon Hye Kwon (Georgia Tech), Daejin Kim, Michelle Kidder, Barry Spencer, Robert Jubin, Ramesh Bhave (ORNL), Sankar Nair (Georgia Tech)

Adsorption of Iodine and Tritium from UNF Reprocessing Off-Gas Streams

B. B. Spencer, S. H. Bruffey, J. F. Walker, R. T. Jubin (ORNL)

Dry Pretreatment of Used Nuclear Fuel for Tritium Removal: A Review

G. D. DelCul (ORNL), J. A. Johnson (ORNL UT-Battelle), B. B. Spencer, R. D. Hunt, R. T. Jubin (ORNL)

Methods to Capture the Tritium Released by Recovery/Recycle of Zirconium from Used Fuel Cladding: A Review

B. B. Spencer, G. D. DelCul (ORNL)

Economics and Cost Analysis of Spent Fuel Cycle-Panel

Heat Storage and Hybrid Energy Systems

Implications of Zero-Carbon Nuclear Renewable Economy: Equity, Economics, and Social Costs

Charles W. Forsberg (MIT)

Revenue Opportunities through Ancillary Services for Nuclear Power Plants with Integrated Firebrick Resistance-Heated Energy Storage (FIRES)

Daniel J. Curtis, Charles W. Forsberg (MIT)

Optimizing Short-Term Operation of a FIRES-Like Industrial Heat Supply Thermal Energy Storage System

Daniel J. Curtis, Nestor Sepulveda, Charles W. Forsberg (MIT)

Design of a Thermal Energy Storage System for SMR's

Konor Frick, J. Michael Doster (NCSU)

Synthetic Heat Transfer Fluids as Thermal Energy Storage Media for Existing NPPs

Daniel Franken, Jacob Edwards, Hitesh Bindra (Kansas State Univ), Piyush Sabharwall (INL)

University Research in Fuel Cycle and Waste Management-I

Insights and Trends from a Literature Assessment of the Thorium Fuel Cycle

Timothy M. Ault, Steven L. Krahn (Vanderbilt Univ), Andrew Worrall (ORNL), Bethany L. Burkhardt, Colin Caldwell, Allen G. Croff (Vanderbilt Univ)

Complexation and Solvent Extraction Studies of High Valency Actinides by Hard/Soft Donor Schiff Base Ligands

Christian Bustillos, Mikael Nilsson (Univ of California, Irvine)

Aggregation and Synergism in Solvent Extraction Processes for Used Nuclear Fuel

A. Jackson, M. Nilsson (Univ of California, Irvine)

Trisulfonamide Ligands for F-Metal Complexation and Extraction from Alkaline Solutions

Evgen V. Govor, Raphael G. Raptis, Konstantinos Kavallieratos (Florida International Univ)

Re-Evaluation of the Gamma Radiolysis Radiation Chemistry of Neptunium

G. P. Horne, S. P. Mezyk (California State Univ, Long Beach)

Determination of Activity of Neodymium(III) in Molten Eutectic LiCl-KCl using Electrochemical Methods

Prashant Bagri, Michael Simpson (Univ of Utah)

Development and Optimization of Normal Pulse Voltammetry for Real Time Analysis of Electrorefiner Salt with High Concentrations of MgCl₂ and UCl₃

Chao Zhang, Michael Simpson (Univ of Utah)

Consolidated Storage of Commercial Used Fuel

Overview of the U.S. Department of Energy, Office of Nuclear Energy's Nuclear Fuel Storage and Transportation Planning Project

W. Mark Nutt (ANL), Robert L. Howard, Matthew R. Feldman, Joshua J. Jarrell (ORNL), Joe T. Carter (SNL)

U.S. Department of Energy, Office of Nuclear Energy, Nuclear Fuel Storage and Transportation Planning Project Modeling Tools

Joshua J. Jarrell (ORNL), Mark D. Abkowitz (Vanderbilt Univ), Robert Joseph III (ORNL), Michael Samsa, Natalia Saraeva (ANL), John M. Scaglione (ORNL), Jim St. Aubin, Casey Trail (ANL)

Summary of Industry Task Orders Completed by the U.S. Department of Energy, Office of Nuclear Energy's Nuclear Fuel Storage and Transportation Planning Project

Robert L. Howard (ORNL), Joshua J. Jarrell, Matthew R. Feldman, Joe T. Carter (SRNL)

Cataloguing Past Incidents in Transporting Spent Nuclear Fuel

Kevin J. Connolly (ORNL), Ronald B. Pope (ANL)

Risk-Informed Maritime Spent Fuel Transportation

Robby Christian, Hyun Gook Kang (KAIST)

Cosmic Ray Muon Radiography of Spent Fuel in Dry Storage Casks

J. Matthew Durham, Elena Guardincerri, Chris Morris, Daniel Poulson, Jeffrey Bacon (LANL), David Chichester (INL), Joseph Fabritius, Shelby Fellows, Kenie Plaud-Ramos, Deborah Morley (LANL), Philip Winston (INL)

Investigation of Imaging Spent Nuclear Fuel Dry Casks Using Cosmic Ray Muons

S. Chatzidakis, C. K. Choi, L. H. Tsoukalas (Purdue Univ)

Proposed Muon Radiography Method for Spent Fuel Cask Interrogation

Daniel Poulson, Matt Durham, Elena Guardincerri (LANL), Adam Hecht (Univ of New Mexico), Christopher Morris (LANL)

University Research in Fuel Cycle and Waste Management -II

Uranium from Seawater Cost Analysis: Recent Updates

Margaret Flicker Byers, Erich Schneider (Univ of Texas, Austin)

Co-Adsorption of I₂ and H₂O on Ag^oZ and Kinetics of Iodine Silver Reaction

Yue Nan (Syracuse Univ), Austin P. Ladshaw, Sotira Yiacoumi (Georgia Tech), Costas Tsouris, David DePaoli (ORNL), Lawrence L. Tavlarides (Syracuse Univ)

Capacity of ETS-10 Supported Carbon Nanosorbent for Removal of Multicomponent from Off-Gas Stream

Kai M. Coldsnow, Sachin U. Nandanwar, Austin Porter, Vivek P. Utgikar (Univ of Idaho), Piyush Sabharwall (INL), D. Eric Aston (Univ of Idaho)

Adsorption Modeling at the Front and Back Ends of the Nuclear Fuel Cycle

Austin Ladshaw (Georgia Tech), Yue Nan, Lawrence L. Tavlarides (Syracuse Univ), David DePaoli, Costas Tsouris (ORNL), Sotira Yiacoumi (Georgia Tech)

Simulated Gamma Doses to Coating Materials for use in High Level Waste Packages

Abigail H. M. Casey, Lucienne Behar, Sean P. Kerrigan, A. Leigh Winfrey (Unv of Florida)

Charge Carrier Diffusion Length Determination in 4H-SiC Schottky Alpha Detectors

Joshua T. Jarell, Benjamin Reinke, Max Chaiken, Brandon Wilson, Wolfgang Windl, Brian Esser, Lei Cao, Thomas Blue (Ohio State)

Advanced Fuel Cycle Technology

Thermodynamic Assessment of LiCl-KCl-PuCl3 Ternary System

Wentao Zhou, Jinsuo Zhang (Ohio State)

Investigation on Reaction Probabilities for Cyclic Voltammetry of Zirconium in LiCl-KCl Eutectic Molten Salt via Reverse-Engineering Method

Samaneh Rakhshan Pouri (MNE), Supathorn Phongikaroon (Virginia Commonwealth Univ)

An Initial Study of Uranium Morphology in Fused LiCl-KCl

Ken C. Marsden (INL), Supathorn Phongikaroon (Virginia Commonwealth Univ)

Electrodeposition of Actinides on a Semiconductor Detector for Concentration Monitoring

Milan Stika (Univ of Utah), Max Chaiken, Joshua Jarrell, Thomas Blue, Lei R. Cao (Ohio State), Michael Simpson (Univ of Utah)

Metal Oxide Electrolytic Reduction using Glassy Carbon as Anode

Haiyan Zhao (Univ of Idaho), Shelly X. Li (INL), Eric Song (Univ of Idaho)

Comparison of Advanced Processing of Irradiated UO₂ Fuels and NpO₂ Targets

E. D. Collins, D. E. Benker, D.W. DePaoli, L. H. Delmau, R. M. Wham (ORNL)

Mechanical Analysis to Study Pore Formation Mechanism in U-Mo/Al Dispersion Fuel

Gwan Yoon Jeong (Ulsan Inst), Yeon Soo Kim (ANL), Kyu Hong Lee (KAERI), Dong-seong Sohn (Ulsan Inst)

Recycle and Reuse of Used Nuclear Fuel Resources

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

Craig Barnes, Michael Kandziolka, Michael Ortiz, Eric McAnly (Univ of Tennessee), Guillermo Danie DelCul (ORNL), David F. McLaughlin (Westinghouse)

Separation of Zirconium from Zircaloy-2 for Spent Nuclear Fuel Cladding Applications using a Chloride Volatility Process

Rosendo Borjas Nevarez (UNLV)

First-Principles Study of Mechanical Properties of Zirconium Alloys and Hydrides

Eunja Kim (UNLV), Philippe F. Weck, Veena Tikare (SNL), Frederic Poineau, Ken Czerwinski (UNLV), John A. Mitchell (SNL)

Development of Chlorination Process for Cladding Hull Waste and Its Combination with Pyroprocessing

Min Ku Jeon, Jin-Mok Hur, Do-Hee Ahn (KAERI)

Phase Equilibria in Systems Relevant to Pyroprocessing

A. L. Hames (Oregon State Univ), A. Paulenova, M. A. Williamson (ANL)

Mass Inventory Balance and Fuel Breeding Analysis on Transuranic Recycling Option of FBR

Sidik Permana (Bandung Inst of Technology), Mitsutoshi Suzuki (JAEA), Zaki Suud, Abdul Waris (Bandung Inst of Technology), Masaki Saito (Tokyo Inst Technol)

Adsorption and Transport Properties of Zeolite SAPO-34 for Krypton/Xenon Separations

Yeon Hye Kwon, Emily Benjamin, Vivek Pisharodi, Junyoung Hwang (Georgia Tech), Ramesh Bhave (ORNL), Sankar Nair (Georgia Tech)

XAFS Investigation of Uranium Binding by Seawater-Contacted Amidoxime Adsorbents

Carter W. Abney (ORNL), Wenbin Lin (The Univ of Chicago)

Fuel Cycle Analysis

Impacts of Recycling Time on Fuel Cycle Transition

B. Feng, T. Fei, F. Heidet, E. Hoffman (ANL)

Transition Benefits of using Low Enriched Uranium Fuel in Fast Reactors

E.. Hoffman, B. Feng, T. Fei (ANL), A. Worrall (ORNL)

Analysis of Synergistic Fuel Cycle Options with Thorium and Heavy Water Reactors

Timothy M. Ault, Steven L. Krahn (Vanderbilt Univ), Andrew Worrall (ORNL), Allen G. Croff (Vanderbilt Univ)

Value of Information in Fuel Cycle Decision-Making

Urairisa B. Phathanapirom, Erich A. Schneider (Univ of Texas, Austin)

An Iterative Optimization Strategy for Nuclear Reactor Design

Akansha Kumar, Pavel V. Tsvetkov (Texas A&M)

Predicting Fueled Experiment Swelling and Thermal Expansion Using STAR-CCM+

Justin W. Herter (Univ of Michigan)

Developing Soret Transport Coefficients for Lanthanides from Experimental Results

C. W. Arnold, C. Unal (LANL)

Fuel Cycle and Waste Management: General

TREAT Transient Test Reactor Restart Status

John D. Bumgardner (INL/TREAT Restart Program)

Nuclear Forensics for Irradiated Materials using Kernel Regression Models

Kyung ho Jin (Kyung Hee Univ), Jae kwang Kim, Seung Min Lee (Korea Inst of Nuclear Nonproliferation and Control), Gyun young Heo (Kyung Hee Univ)

The Safe Guards Analysis Toolbox for Non-Proliferation Modeling

Nicolas Shugart, Jeffrey King (CSM)

Radiological Consequences of Hydrogen Explosions in Vessels and Piping at the WTP

Roger Lanning, Richard I. Smith (Bechtel National)

A Comparison of the U.S. Nuclear Regulatory Commission Technical Evaluation for the Zion and La Crosse License Termination Plans with a Focus on Release Criteria

Leah Parks , John B. Hickman, Marlayna Vaaler (NRC)

Cement Solidification of Residual Metal Oxide from Radioactive Waste

Daeseo Koo, Gye-Nam Kim, Jong-Won Choi (KAERI)

Fusion Energy-Technology and Applications

ITER Port Interspace Pressure Calculations

Juan J. Carbajo, Walter Van Hove (ORNL)

Experimental Activities with the IELLLO Lithium-Lead Facility

Andrea Gabriele (DENERG - Politecnico di Torino), Marco Utili (ENEA)), Luigi Candido(DENERG - Politecnico di Torino), Alessandro Venturini (Pisa Univ), Massimo Zucchetti (Politecnico di Torino)

Neutronics of Advanced-Fuel Fusion Experiments with DT Triggering

Massimo Zucchetti (Politecnico di Torino), Marco Riva (UCLA)

Investigation of the Effects of Hydrogen Atoms Concentration on the Tungsten Sigma 5 (310) Symmetric Tilt Grain Boundary Strength

Kabiru Atiku, Xue Yang (Texas A&M)

Kinetic Monte Carlo Simulation of Hydrogen Diffusion in Tungsten

Xue Yang, Wasiu O. Oyeniyi (Texas A&M)

Theoretical Calculation and Simulation Studies of Axisymmetric Plasma and Halo Current Analysis in EAST

Shahab Uddin Khan (Inst of Plasma Physics), Salah Ud-Din Khan (King Saud Univ), Yuntao Song (Inst of Plasma Physics)

Human Factors, Instrumentation and Controls: Software Dependability and Advanced Technologies

Importance Ranking of Software Dependability Attributes in the Nuclear Industry

Boyuan Li, Fuqun Huang (Ohio State), Ted L. Quinn (Technology Resources), Carol S. Smidts (Ohio State)

Development of an Automated Software Reliability Tester for Digital I&C

Brent D. Shumaker, Gregory W. Morton (AMS)

Software Dependability

George Hughes (Schneider-Electric)

Software Dependability for Digital Instrumentation and Control Systems in Nuclear Power Plants-Lessons Learnt from a DOE Sponsored Project

Carol S. Smidts, Fuqun Huang, Boyuan Li (Ohio State), Ted L. Quinn (Technology Resources)

Dependability Assessment of Software for Safety Instrumentation and Control Systems

Richard T. Wood (Univ of Tennessee), Robin E. Bloomfield (Adelard LLP), Nguyen Thuy (EdF R&D)

Development of Criteria for Hardware Descripted Language Programmed-Devices for Safety Systems in Nuclear Power Plants in the U.S.

Steven A. Arndt, Rossnyev Alvardo, Bernard Dittman, Michael Waterman (NRC)

Automated Work Package: Initial Wireless Communication Platform Design, Development, and Evaluation

Ahmad Al Rashdan, Vivek Agarwal (INL)

The Role of the Nuclear Science User Facilities in Nuclear Energy Research and Development

Brenden J. Heidrich (INL)

MCNP 6.2.0 Delayed-Particle Production Improvements

J. R. Tutt, G. W. McKinney, T. A. Wilcox, G. E. McMath (LANL)

Computed Tomography by Combining Transmission and Scatter Radiography Methods

Michael J. Liesenfelt, James Baciak, Edward Dugan (Univ of Florida), Greg Grissom (Georgetown Railroad Equipment Co.)

Thermal Flux Maximization from a DD Neutron Generator

Walid A. Metwally, Mohammed Ballaith (Univ of Sharjah), Allan X. Chen (Adelphi Technology)

Flux Estimation of a PuBe source using Delayed Gamma Neutron Activation Analysis

Akanchha Fnu, Shivam Singh (IIT), Matthew Barrett (Texas A&M) Shikha Prasad (IIT)

Investigation of Energy Selective Neutron Imaging at the PULSTAR Reactor

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

Response of Ferroelectric Polyvinylidene Fluoride under Pulsed Fast Neutron Irradiation

Wenfeng Liang, Jian Wu, Yi Lu (CAEP)

Current Issues in Computational Methods-Roundtable

Transport Methods

Radiation Transport in Random Media with Large Fluctuations

Aaron J. Olson, Anil K. Prinja (Univ of New Mexico), Brian C. Franke (SNL)

Nonclassical Particle Transport in the 1-D Diffusive Limit

Richard Vasques, Rachel N. Slaybaugh (Univ of California, Berkeley), Kai Krycki (Aachen Inst for Nuclear Training GmbH)

An Atomic Mix Closure for Stochastic Media Transport Problems

Shawn D. Pautz, Brian C. Franke (SNL)

Modified Closures in Monte Carlo Algorithms for Diffusive Binary Stochastic Media Transport Problems

Patrick S. Brantley (LLNL)

The Improved Simple Corner Balance Method and Efforts to Enhance its Computational Performance

Peter G. Maginot, Peter N. Brown, Adam J. Kunen, Teresa S. Bailey (LLNL)

High Order Finite Elements S_N Transport in X-Y Geometry on Meshes with Curved Surfaces

Douglas N. Woods (Oregon State Univ), Thomas A. Brunner (LLNL), Todd S. Palmer (Oregon State Univ)

On the Degradation of the Effectiveness of Nonlinear Diffusion Acceleration with Parallel Block Jacobi Splitting

Sebastian Schunert, Yaqi Wang, Javier Ortensi, Frederick Gleicher, Benjamin Baker, Mark DeHart, Richard Martineau (INL)

Accelerated Monte Carlo Fission Source Convergence with Fission Matrix and Kernel Density Estimators

Steven P. Hamilton, Gregory G. Davidson, Thomas M. Evans Kaushik Banerjee (ORNL)

Mathematics and Computation: General

Interactive Visualization of Multi-Group Cross Sections on High-Fidelity Spatial Meshes

Logan Abel, William Boyd, Benoit Forget, Kord Smith (MIT)

Group Structure Optimization using the PyGroup Code

Ce Yi (Georgia Tech), Glenn E. Sjoden, Christopher Edgar (Georgia Tech)

A Backward Euler Doubling Feasibility Study Based on Thorium Series Cascade

K. Huang, Y. Li (Jiaotong Univ), B. Ganapol (Univ of Arizona)

Pin-by-Pin Core Calculation with an NEM-Based Two-Level Hybrid CMFD Algorithm

Seongho Song, HwanYeal Yu, Yonghee Kim (KAIST)

Error Propagation for Response Matrix Methods in the Many Node Limit

Kyle Remley, Gabriel Kooreman, Farzad Rahnema (Georgia Tech)

Initial Validation of the Neutron Physics Codes in COSINE using the MIT BEAVRS Benchmark

Lei Shi, Zhanquan Liu, Guoping Quan, Hui Yu, Yixue Chen (SNPSDC)

Implementation of Material and Geometry Criticality Search in RMC Code

Gang Wang, Ganglin Yu, Kan Wang (Tsinghua Univ)

Multi-Node and Multi-Core Performance Studies of a Monte Carlo Code RMC

Feng Yang, Ganglin Yu, Jin Gang Liang, Kan Wang (Tsinghua Univ)

Uncertainty Quantification and Sensitivity Analysis Methods

The Uncertainty Due to Correlated Mass, Volume, and Density When Mass and Density are Measured

Jeffrey A. Favorite (LANL), Zoltan Perko (Massachusetts General Hospital)

Nuclear Data Uncertainty Quantification for Adjoint-Weighted Quantities via XGPT

Manuele Aufiero, Michael Martin, Massimiliano Fratoni (Univ of California, Berkeley)

Inverse Uncertainty Quantification of Reactor Simulation with Polynomial Chaos Surrogate Model

Xu Wu, Tomasz Kozlowski (Univ of Illinois)

TRACE Code Validation of BWR SVEA Fuel Assembly Spray Cooling

Travis Mui, Tomasz Kozlowski (Univ of Illinois)

A New CE TSUNAMI-3D Capability for Calculating Undersampling Metrics and Biases

Christopher Perfetti, Bradley Rearden (ORNL)

An Efficient Sampling-Based Method for Sensitivity and Uncertainty Analysis Through RAVEN

C. Wang, P. W. Talbot, C. Rabiti, A. Alfonsi, D. Mandelli, J. Cogliati (INL)

Further Investigation of Employing Binomial Small-Sample Estimator in MLROM

Mohammad G. Abdo (NCSU), Hany S. Abdel-Khalik (Purdue Univ)

Estimation of Uncertainties of Wall Temperature Accomplished by Model Calibration Technique Using Small to Large Scale Reflooding Test Data

Jaeseok Heo, Seung-Wook Lee, Kyung Doo Kim (KAERI)

Particle-Image Velocimetry Sensetivity through Automatic Differntiation

Rodolfo Varela, Kyle Horne (Univ of North Texas)

Criticality for Spent Fuel Pools and Transport Casks

Solving the Interface Problem in Criticality Analysis

Charles Rombough (CTR Technical Services, Inc.), Dale Lancaster (NuclearConsultants.com), Robert Hall (Dominion)

New Approach to Eccentric Positioning of Fuel Assemblies in a Spent Fuel Pool

Dale B. Lancaster (NuclearConsultants.com), Bob Hall (Dominion), Charles Rombough (CTR Technical Services, Inc.)

Fission Gases in Spent Fuel Pool Criticality Analysis

Dale Lancaster (NuclearConsultants.com), Bob Hall (Dominion), Matthew Harris (Curtiss-Wright), Charles Rombough (CTR Technical Services, Inc.)

Impact of Concrete Composition on Criticality at Nuclear Power Plants

Dale Lancaster (NuclearConsultants.com), Bob Hall (Dominion), Matthew Harris (Curtiss-Wright), Charles Rombough (CTR Technical Services, Inc.)

Apparent Monte Carlo Source Convergence Problem with BWR Fuel Depleted with Partial Control Blade Insertion

W. J. Marshall, B. J. Ade, S. M. Bowman (ORNL)

Data, Analysis and Operations in Nuclear Criticality Safety-I

Validation of MCNP5 for use in Calculating Temperature Coefficients of Reactivity for the SHINE System

Tracy E. Radel, Eric N. Van Abel (Shine Medical Technologies)

Validation of KENO Thermal Moderator Doppler Broadening Method in SCALE 6.2 Beta5 Using Continuous-Energy B-VII.1 Library

T. A. Eckleberry (Univ of Tennessee), W. J. Marshall (ORNL), E. L. Jones, G. I. Maldonado (Univ of Tennessee)

A Solid of Revolution Time Study using COG11.1 and MCNP6.1

William J. Zywiec, David P. Heinrichs (LLNL)

An Investigation of MCNP6.1 Beryllium Oxide S(α, β) Cross Sections

Raymond F. Sartor, Natasha N. Glazener (LANL)

Benchmarking of the Updated Resolved Resonance Region Evaluations of Copper

Vladimir Sobes (ORNL), Luiz C. Leal (IRSN, Inst of Radiation Protection), Dennis E. Mennerdahl (E Mennerdahl Systems)

NJOY21: A Successor to the NJOY Nuclear Data Processing System

Austin McCartney, Jeremy Loyd Conlin, Daniel Rehn (LANL)

Data, Analysis and Operations in Nuclear Criticality Safety-II

A Chemistry Based Criticality Safety Evaluation of the HM-Process Mixer Settlers

Tracy Stover, Stephen Kessler (SRNS)

Incredibility of a Postulated Criticality Event for Enriched Uranyl Nitrate Storage

Tracy Stover, Stephen Kessler (SRNS)

C-400 and C-409 Criticaltiy Incredible Road Map

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

UPF Data Book: A Resource for Standard Data, Dimensions, Equations and Practices Used at UPF for Nuclear Criticality Safety Analyses

Barbara I. Krogfuss (Consolidated Nuclear Security, LLC), Daniel F. Hollenbach, Richard G. Taylor (C. S. Engineering, Inc.)

Limiting Surface Density Method Application to Large Arrays of Highly Heterogeneous Shipping Packages

Tracy E. Stover, James S. Baker, Michael Ratliff, (SRNS)

Data, Analysis and Operations in Nuclear Criticality Safety-III

Subcritical Copper-Reflected Alpha-Phase Plutonium (SCRaP) Integral Experiment Design

R. Bahran, J. Hutchinson (LANL)

Preliminary Flattop-25 Reevaluation Results

Jeffrey A. Favorite (LANL)

Artificial Neural Network Representation of Dynamic Criticality Excursion Experiment Data

Peter L. Angelo (Y-12 NSC)

A Novel Method for Determination of Equivalence Factor of External Neutron Source to Fundamental-Mode Source

Lingli Song (CAE), Hui Gao (CAEP)

Uncertainty as a Function of Time for Subcritical Experiment Parameters Using the Hage-Cifarelli Formalism

J. Hutchinson, T. Grove, M. Smith-Nelson (LANL)

Measurements of Neutron Importance Distribution in ²³⁵U Fast Critical Reactor

Lingli Song, Yanpeng Yin, Haojun Zhou (CAEP)

Sharing of Good Industry Practices in Criticality Safety-Panel

ANS-8 Standards-Forum

Nuclear Installations Safety: General-I

Thermal-Hydraulic Design of a Fluoride High-Temperature Demonstration Reactor

Juan J. Carbajo, Lou Qualls, Nicholas R. Brown (ORNL)

Moving Beyond Traditional Tornado Missile Impact Analysis

Derrick Watkins, John Svet (Tobolski Watkins Engineering, Inc.)

Advanced Computational Accident Scenario Modeling for Safety Margin Economic Analysis

Thomas Riley, John Jordahl, Andrew Klein (Oregon State Univ)

Performance Analyses of Passive Containment Cooling System for a Concrete Type Containment

Pyeong-Mo Jeong, Dong-Wook Jerng, (Chung-Ang Univ), Han Gon Kim (Central Research Inst, Korea Hydro & Nuclear Power Co.)

External Events Analysis for LWRS/RISMC Project: Methodology Development and Early Demonstration

Carlo Parisi, Steven Prescott, Richard Yorg, Justin Coleman, Ronaldo H. Szilard (INL)

Nuclear Installations Safety: General-II

Development of F&B Operation Strategy with LPSI and H-SIT

In Seop Jeon, Hyun Gook Kang (KAIST)

Reliability Assessment of Safety-Critical Network Communication in a Digitalized Nuclear Power Plant

Sang Hun Lee, Hyun Gook Kang (KAIST)

Zinc Corrosion in Borated, Buffered Post-LOCA Solutions

Janet Leavitt (AlionSciTechnol), Shaoqiang Guo, Yakun Zhu, Jinsuo Zhang (Ohio State), Jainisha Shah, Bruce Letellier (AlionSciTechnol)

Corrosion of Aluminum in the Chemical Environment after a Loss of Coolant Accident (LOCA)

Shaoqiang Guo (Ohio State), Janet J. Leavitt (AlionSciTechnol), Jinsuo Zhang (Ohio State)

The DOE Unreviewed Safety Question Process, Addressing New Information for Credible Nuclear Accidents

Donald Owen, John Abrefah (DNFSB)

New Construction Around the World-Panel,

Advanced/Generation IV Reactors

Techno-Economic Assessment of the Factory Production of Small Modular Reactors

Benjamin Vegel, Jason C. Quinn (Utah State Univ)

All Nuclear Hybrid Superheater Design Method

Paul Marotta, Basil Antar (Univ of Tennessee), Steve L. Krahn (Vanderbilt Univ)

Heat Transfer in a Molten Natural Uranium Nuclear Reactor with Thermal Storage

Neal L. Mann (Neal Mann & Assoc)

Variable Nuclear Electricity with Base-Load Reactor, Closed Brayton Power Cycle and Firebrick Resistance-Heated Energy Storage (FIRES)

Charles W. Forsberg (MIT), Patrick J. McDaniel (Univ of New Mexico)

Nitride Fuel Potential for Power-Uprates

Guillaume Giudicelli, Koroush Shirvan (MIT)

Hybrid Energy Systems-Panel

Radiation Protection and Shielding

Comparing Thick Target Neutron Yield Calculations for Alphas on F-19 using MCNP6 1.1 Beta with TENDL 2012 Libraries

M. L. Fensin, G. E. McMath, M. L. Lockhart, K. A. Miller and M. T. Swinhoe (LANL)

Development of In-Situation Radioactivity Inspection System for Food Materials

Sujung Min Haeyoung Ko, Unjang Lee (ORIONENC)

NORM Concentration Determination in Common Materials in an Urban Environment

Mathew W. Swinney, Douglas E. Peplow, Bruce W. Patton, Andrew D. Nicholson (ORNL)

Hardened Containment Vent System Dose Considerations for FLEX

Julie M. Jarvis, Sharad Jha, Matthew J. Brenner, Paul J. Babel (Bechtel)

The New Modular High-Energy X-ray Source Facility Shielding Design

T. C. McClanahan, C. Crutcher, K. H. Darby, M. Megonigal, A. Moore, L. F. Miller (Univ of Tennessee)

Radiation Protection and Shielding-Roundtable

Computational Tools for Radiation Protection and Shielding

Energetic Light Fragment Production Capability in MCNP6, Le

slie M. Kerby (Univ of Idaho), Stepan G. Mashnik (LANL), Konstantin K. Gudima (Inst of Applied Physics, Academy of Science of Moldova), Arnold J. Sierk, Jeffrey S. Bull, Michael R. James (LANL)

The Solid Angle for a Spherical Surface Source and a Detector with an Arbitrary Aperture: An Elegant Proof

Jeffrey A. Favorite (LANL)

MCNP6 Study of Spatial Fidelity Required for ROC Curve Convergence

G. E. McMath, G. W. McKinney (LANL)

Predicting Future Solar Modulation and Implementation in MCNP6

L. R. Liegey, J. R. Tutt, T. A. Wilcox, G. W. McKinney (LANL)

ADVANTG Workshop

Reactor Physics: General-I

Feasibility Studies on a Hexagonal-Lattice Core for a World-Class Cold Neutron Source

Dylan M. Prevost (Texas A&M), Zeyun Wu, Robert E. Williams (NIST)

Application of Neutron Detection Third Order Time Correlation

Philippe P. Humbert (CEA)

Multi-Physics Simulation of the TRIGA Reactor

Romain Henry, Iztok Tiselj, Luka Snoj (Jozef Stefan Inst)

Physics and Environmental Assessments for a Heavy-Water Moderated, Molten Uranium Reactor Concept

Neal L. Mann (Neal Mann & Assoc)

MC²-3/DIF3D Analysis of the ZPPR-15 Axial Expansion Experiments

M. A. Smith, R. M. Lell, C. H. Lee, R. N. Hill (ANL)

Progress Status of Prototype Generation-IV Sodium-Cooled Fast Reactor-I

PGSFR General Arrangement

Soonki So, Heecheon Chu, Hyun-Kyu Lee, Hae-Gyu Lee (KEPCO E&C)

Overall Reactor System Description of Prototype Gen-IV Sodium Cooled Fast Reactor

Jaewoon Yoo, Jinwook Chang, Hyung-Koo Joo (KAERI),

Overview of PGSFR Project

Tae-Wan Kim, Kyu-Suk Ahn, Jong-Hyuk Baek, Young-Gyun Kim, Won-Seok Park (KAERI)

PGSFR Core Design and Performance Characteristics

Jae-Yong Lim, Sun Rock Choi, Sang Ji Kim (KAERI)

Plant Operation and Control Strategy for the PGSFR

Richard B. Vilim, Taeseung Lee (ANL)

Safety Analyses of Design Basis and Design Extended Condition Events for the PGSFR

Seok Hun Kang, Kwi-Lim Lee, Chi-Woong Choi, Jae-Ho Jeong, Tae-Kyoung Jeong, Kwi-Seok Ha (KAERI)

Metal Fuel Implications on Severe Accident Scenarios

Yoon I. Chang, Mitchell T. Farmer, Adrian Tentner, Arthur E. Wright (ANL)

Progress Status of Prototype Generation-IV Sodium-Cooled Fast Reactor-II

Shielding Design for Prototype Generation-IV Sodium-Cooled Fast Reactor

T. Fei, T. K. Kim, (ANL), S. Yun, S. J. Kim (KAERI)

Computer Code V&V Tests with a Large-Scale Sodium Thermal-Hydraulic Test Facility (STELLA)

Jaehyuk Eoh, Jonggan Hong, SujinYeom, Jewhan Lee, Ji-Young Jeong (KAERI)

Reactor Analysis Methods-I

Dimensionality Reduction Algorithms for Big Nuclear Data Streams with Application to SCALE Cross Sections

Siqi Zhang, Yeni Li (Purdue Univ), Ugur Mertyurek (ORNL), Hany S. Abdel-Khalik (Purdue Univ)

RISMC Industry Application #1 (ECCS/LOCA) Core Characterization Automation: Lattice Codes Interface for PHISICS/RELAP5-3D

Aaron Simon Epiney, Carlo Parisi, Hongbin Zhang, Ronaldo H. Szilard (INL)

Adaptive Sparse-Grid Collocation Uncertainty Quantification Convergence for Multigroup Diffusion

Paul W. Talbot (Univ of New Mexico), Anil K. Prinja (Univ of New Mexico), Cristian Rabiti (INL)

Reactor Physics: General-II

NECP-Cypress: Development and Validation of a 3D PWR Core Analysis Code

Yunzhao Li, Wen Yang, Hongchun Wu, Liangzhi Cao (Xi'an Jiaotong Univ)

Neutron Number Probability Distributions in a Subcritical System Using the Forward Master Equation

Patrick F. O'Rourke, Anil K. Prinja (Univ of New Mexico), Erin D. Fichtl (LANL)

Photo-Transmutation of ¹⁰⁰Mo to ^99mTc with Laser-Compton Scattering Gamma-Ray

Jiyoung Lee, Haseebur Rehman, Yonghee Kim (KAIST)

A Space-Dependent Wielandt Shift for Multigroup Diffusion Eigenvalue Problems

Ben C. Yee, Edward W. Larsen, Brendan M. Kochunas, Yunlin Xu (Univ of Michigan)

Multi-Physics Surrogate Modeling with Dimensionality Reduction

Dongli Huang, Hany S. Abdel-Khalik (Purdue Univ), Cristian Rabiti, Frederick N. Gleicher (INL)

Position-Dependency of Fuel Assembly Homogenization in a Pressurized Water Reactor

Woong Heo, Yonghee Kim (KAIST)

Reactor Analysis Methods-II

Finite Volume Method Based Neutronic Solvers for Steady and Transient Analysis of Molten Salt Reactors

Liangzhi Cao, Tianliang Hu, Hongchun Wu (Xi'an Jiaotong Univ)

A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport: I Diffusion Theory

Tengfei Zhang (Xi'an Jiaotong Univ), E. E. Lewis (Northwestern Univ), M. A. Smith (ANL), W. S. Yang (Purdue Univ)

A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport: II Spherical Harmonics

Tengfei Zhang (Xi'an Jiaotong Univ), E. E. Lewis (Northwestern Univ), M. A. Smith (ANL), W. S. Yang (Purdue University)

Application of SPH Factors to PHWR Lattice Homogenization

Eleodor M. Nichita, Subhramanyu Mohapatra (Univ of Ontario Inst of Tech)

On-The-Fly Treatment of Temperature Dependent Cross Sections in the Unresolved Resonance Regions in RMC Code

Shichang Liu, Jiankai Yu, Kan Wang (Tsinghua Univ)

Implementation and Comparison of Different Algorithms for on the Fly Doppler Broadening in RMC Code

Yuan Yuan, Shichang Liu, Kan Wang (Tsinghua Univ)

Reactor Physics Design, Validation and Operational Experience

Model Calibration vs. Physics Guided Coverage Mapping: Case Study-Pressure Drop Calculations

Jia Zhou, Hany S. Abdel-Khalik (Purdue Univ), Nam T. Dinh (NCSU)

Evaluation of B&W UO₂/ThO₂ VIII Experimental Core: Criticality and Thermal Disadvantage Factor Analysis

Carlo Parisi (INL), Emanuele Negrenti (ENEA)

Design of a Commercial Scale Accelerator Driven Subcritical Aqueous Assembly

Eric N. Van Abel, Gregory R. Piefer, Tracy E. Radel (Shine Medical Technologies)

Characterizing the Thermal Column Beam in the University of Massachusetts Lowell Research Reactor

C. Johnson, S. K. Aghara, O. Dim (Univ of Massachusetts Lowell)

Reactor Physics: General-III

A Comparison of Modeling Strategies for Additively Manufactured HFIR Control Elements

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

Reactivity Coefficient Calculation for a Low-Power LEU Research Reactor

Zeyun Wu, Robert E. Williams, Thomas H. Newton (NIST)

Coupling CTF to MPACT for Improved Thermal-Hydraulic Feedback for Transients

Andrew R. Gerlach, John C. Lee (Univ of Michigan)

EBR-II Static Neutronic Calculations by PHISICS/MCNP6 Codes

Paolo Balestra (ENEA), Carlo Parisi (INL)

Selected Profiles of Burnup and Isotopic Concentrations in Pebble Bed High Temperature Reactor Fuel

Hans D. Gougar (INL)

Enhanced Shuffling and Fuel Management Capability in PHISICS Code

Andrea Alfonsi (INL), Angelo Zoino (Univ of Rome "La Sapienza"), Cristian Rabiti (INL), Fabio Giannetti, Gianfranco Caruso (Univ of Rome "La Sapienza")

Computational Thermal-Hydraulics-I

Solving Drift-Flux Model Using High-Resolution Spatial Discretization Scheme

Ling Zou, Haihua Zhao, Hongbin Zhang (INL)

Assessment of Macroscopic k-e Model of CUPID for a Subchannel Analysis

Seung-Jun Lee, Han Young Yoon (KAERI), Seok Jong Yoon, Hyoung Kyu Cho (Seoul Natl Univ)

Modeling the Effect of Evaporative Flux and Colloidal Aggregation on Crud Deposition

Smreeti Dahariya, Hitesh Bindra (Kansas State Univ)

Code Validation of a SBLOCA Test in SMART Integral Test Loop

Byong Guk Jeon (KAERI), Yeon-Sik Cho (System Engineering and Technology Co.), Hwang Bae, Sung-Uk Ryu, Yeon-Sik Kim, Sung-Jae Yi, Hyun-Sik Park (KAERI)

Analysis of Reverse Flow Restriction Device to Prevent Dryout Fuel Damage during BWR Instability

Majdi Ibrahim Radaideh, Tomasz Kozlowski (Univ of Illinois), Yousef M. Farawila (Farawila et al., Inc.)

Comparison of Calculated and Experimental Results for a Boiling/Condensing Experimental Facility

Juan J. Carbajo, Joel L. McDuffee, David K. Felde (ORNL)

Scaling and Design Analysis of a Sub-Scale, Reduced Temperature Stratified Flow Separate Effects Test Facility for the Experimental Investigation of Air Ingress in a High Temperature Reactor System

Joshua Graves, Andrew Klein, Ian White (Oregon State Univ)

Advanced Test Reactor Mini-Plate Hydraulic Testing

G. D. Latimer, W. R. Marcum (Oregon State Univ), W. F. Jones (INL)

Scaling Analysis of Vortex Shedding between Inline Plates

T. K. Howard, W. R. Marcum (Oregon State Univ), W. F. Jones (INL)

Convective Heat Transfer in Decay Heat Exchanger of Sodium-Cooled Fast Reactor

Jonggan Hong, Jaehyuk Eoh, Sujin Yeom, Ji-Young Jeong, Tae-Ho Lee (KAERI)

APR1400 In-Core Instrumentation Penetration Failure by Zirconia Melt

Sang Mo An, Jaehoon Jung, Hwan Yeol Kim (KAERI)

Experimental Data and Analysis for a New Irradiation Facility

Joel L. McDuffee (UT-Battelle), Juan J. Carbajo, David Felde (ORNL)

Measurement of Void Fraction Distribution in Steam-Water Two-Phase Flow in a 4Ã-4 Bundle at 2 MPa

Wei Liu, Taku Nagatake, Mizuhiko Shibata, Kazuyuki Takase, Hiroyuki Yoshida (JAEA)

Computational Thermal-Hydraulics-II

Description of a Dry Cask Simulator for Measuring Internal and External Thermal-Hydraulic Performance

S. G. Durbin, E. R. Lindgren (SNL), A. Zigh (NRC)

Wire-Wrapped Fuel Pin Effect of Bundle Size on Temperature Distribution for Uniform Heat Flux

L. Brockmeyer, L. Carasik (Texas A&M), E. Merzari (ANL), Y. Hassan (Texas A&M)

On the Modeling of Wall Heat Flux Partitioning in Subcooled Flow Boiling

Zeyong Wang (RPI), Dillon R. Shaver (ANL), Michael Z. Podowski (RPI)

Turbulence Model Study for Pressure and Velocity Distributions for Molten Salts in a Crossflow Tube Bundle

L. B. Carasik (Texas A&M), D. R. Shaver (ANL), Y. A. Hassan (Texas A&M)

Multiple RANS Scheme for the CFD Simulation of PWR

Guangliang Chen, Zhijian Zhang, Zhaofei Tian (Harbin Engineering Univ)

Proposal Writing 101-Panel

Nuclear Politics: Perspectives from Nuclear Advocates-Panel

Ask the Public Policy Committee Anything-Panel

Knowledge Transfer and Retention-Panel

POSTER SESSION

Uncertainty Analysis in Critical Configurations of SORA Mockup

Xiaobo Liu (Inst of Nuclear Physics and Chemistry), Margaret Marshall, John Darrell Bess (INL)

Study on Gaseous and Liquid Radioactive Effluents in AP1000 Plants

Li Huaibin, Mao Lanfang (Shanghai Nuclear Engineering Research & Design Inst)

The MELCOR Analysis of Chinshan Nuclear Power Plant Spent Fuel Pool for Fukushima-Like Accident

Jong-Rong Wang (Nuclear and New Energy Education and Research Foundation), Yu Chiang (Natl Tsing Hua Univ), Yung-Shin Tseng (Nuclear Science and Technology Development Center), Hao-Tzu Lin (INER), Shao-Wen Chen (Natl Tsing Hua Univ), Wen-Sheng Hsu (Nuclear Science and Technology Development Center), Jyh-Tong Teng (Chung Yuan Christian Univ), Chunkuan Shih (Nuclear and New Energy Education and Research Foundation)

Importance of Plutonium Turnings in Criticality Safety

Andrew R. Wysong (LANL), Chelsea L. Weaver (Univ of New Mexico)

Fuel Cycle study to Developing a Viable Long Term Nuclear Power Scenario for the UK

Daniel Mathers, Robert Gregg (NNL)

Uncertainty Quantification with MCMC Method and BFBT Data

Guojun Hu, Tomasz Kozlowski (Univ of Illinois)

Design of a Supercritical Carbon Dioxide Corrosion Test Rig for Tube-to-Tube Sheet Joint and High Temperature Insulation Testing

B. R. He, N. H. Haneklaus, J. E. Bickel, D. Krumwiede, P. Hosemann, P. F. Peterson (Univ of California, Berkeley)

Corrosion Testing of TiN on Steel Substrates for use in Waste Packages

John R. Echols (Univ of Florida), Michael A. Fusco (NCSU), Abigail H. M. Casey (Univ of Florida), A. Leigh Winfrey (Univ of Florida)

A Dual ALPHA/GAMMA Imaging Tool to Manage Decommissioning Operations

Charly Mahe, Mehdi Ben Mosbah, Marie Cuozzo, Julien Venara (CEA)

Validation of an Analytical Model for Therapeutic and Stray Dose Calculations of 6 MV Photon Beams

Lydia J. Jagetic, Wayne D. Newhauser (Louisiana State Univ), Robert Carver (Mary Bird Perkins Cancer Center), Rui Zhang (Louisiana State Univ)

Initial Application of the Reactivity Method to Analyze KSU TRIGA Fuel

Saqr Alshogeathri, Jeffrey A. Geuther, Jeremy A. Roberts (Kansas State Univ)

Investigation of Portable Event-Based Monte Carlo Transport Using the NVIDIA Thrust Library

Ryan C. Bleile, Patrick S. Brantley, Shawn A. Dawson, Matthew J. O'Brien (LLNL), Hank Childs (Univ of Oregon)

McStas Analysis of Monoenergetic Thermal Neutron Beam Generation for Total Cross Section Measurements

N. C. Sorrell, Q. Cai, A. I. Hawari (NCSU)

CE TSUNAMI-3D Algorithm Improvements in SCALE 6.2

Christopher Perfetti, Bradley Rearden (ORNL)

Updating a PWR Simulator in Python

Richard L. Reed, Jacob W. Hayhurst, Shravan D. Gangadhara, Jeremy A. Roberts (Kansas State Univ)

Sensitivity Study of Void Coefficients in the SHEBA-II Critical Assembly using MCNP6

Megan R. Smith (NCSU), Adam C. Davis, Donald J. Dudziak (LANL)

Development of a Phoswich Neutron Detector with Energy Spectroscopy Capability

Jessica Hartman, Alexander Barzilov (UNLV)

Acceleration Techniques using ADVANTG for the MDF Design and Optimization

T. C. McClanahan (Univ of Tennessee), F. X. Gallmeier, E. B. Iverson (ORNL)

Plenary Session

Accident Tolerant Fuels

Advanced Nuclear Fuels and Materials Development and Philosophy of the DOE Advanced Fuels Campaign

Jon Carmack, Shannon M. Bragg-Sitton (INL)

Overview of LWR Accident Tolerant Fuel Development in the U.S.

Shannon M. Bragg-Sitton, Jon Carmack (INL)

Advancements in FeCrAl Alloys for Enhanced Accident Tolerant Fuel Cladding for Light Water Reactors

Kevin G. Field, Yukinori Yamamoto (ORNL), Samuel A. Briggs (Univ of Wisconsin, Madison), Maxim N. Gussev, Kinga A. Unocic, Bruce A. Pint (ORNL), Raul B. Rebak (GE Global Research Center), Lance L. Snead, Kurt A. Terrani (ORNL)

Westinghouse Accident Tolerant Fuel Program

E. Lahoda, S. Ray, P. Xu, F. Boylan (Westinghouse)

Development of SiC-Based Cladding for Accident Tolerant Fuels

Yutai Katoh, Caen Ang, Takaaki Koyanagi, Gyanender Singh, Kurt Terrani (ORNL)

Advanced Fuels and Fuel Cycle-I

Transmutation Fuels Development in the Advanced Fuels Campaign

Steven L. Hayes, Heather J. M. Chichester, Randall S. Fielding, Michael T. Benson, W. Jon Carmack (INL)

The Research of MOX Fuels in Japan

Masato Kato (JAEA)

Fuels and Materials Challenges for the Very High Temperature Reactor

David A. Petti, Richard Wright, Will Windes, Paul A. Demkowicz (INL)

Monolithic U-10Mo Fuel Development for U.S. High Performance Research Reactors

James I. Cole, Barry H. Rabin, Barry H. Rabin, Irina Glagolenko, Nicolas Eric Woolstenhulme, Adam B. Robinson, Dennis D. Keiser, Hakan Ozaltun, Walter J. Williams, Francine J. Rice, Glenn A. Moore, Jian Gan, James A. Smith, Mitchell K. Meyer, Daniel M. Wachs (INL), Gerard L. Hofman, Yeon Soo Kim (ANL)

Highlights from the Postirradiation Examination of AFC-3A and AFC-3B

Jason M. Harp, Heather J. M. Chichester (INL)

Light Water Fuels and Structural Materials

Materials Challenges and Experimental Approaches to Understanding Long-Term Materials Behavior for Extended Nuclear Plant Operations

Keith J. Leonard (ORNL)

Zirconium Alloy Corrosion and Hydrogen Pickup

Arthur T. Motta (Penn State), Adrien Couet (Univ of Wisconsin-Madison)

The High Burnup Structure: Overview of Properties and Recent Findings

V.V. Rondinella, T.A.G. Wiss, F. Cappia, M. Marchetti, D. Papaioannou (EC-JRC-ITU)

Progress in Assessment of the Behavior of Light Water Reactor Nuclear Fuel Materials during Off-Normal Conditions

A. T. Nelson, J. T. White, E. S. Wood, and K. J. McClellan (LANL)

Thermal Aging Degradation of Cast Stainless Steels in LWR Systems

Thak Sang Byun (PNNL), Ying Yang (ORNL), Nicole R. Overman (PNNL), Keith J. Leonard (ORNL)

Modeling and Simulation-I

An Overview of Material Models in the BISON Fuel Performance Code

R. L. Williamson (INL)

Meso-Scale Fuel Performance Modeling using the MARMOT Code

Yongfeng Zhang (INL), Michael Tonks (Penn State), Daniel Schwen (INL), David Andersson (LANL)

Grizzly: A Multi-Scale and Multi-Physics Tool to Model Aging of Nuclear Power Plant Components

Pritam Chakraborty, Benjamin Spencer (INL), Marie Backman (Univ of Tennessee), William Hoffman (Univ of Idaho), Xian-Ming Bai, Yongfeng Zhang (INL)

Multiscale Modeling of Accident Tolerant Fuels under the NEAMS ATF Program

Jason Hales, Kyle A. Gamble (INL)

Atomistic Simulations in Support of UO₂ Fuel Performance Modeling

David Andersson (LANL)

Advanced Characterization

Characterization of Ion Implantation and Irradiation Effects in Interface-Dominated Metallic Composites

N. Li (LANL), W. Han (Xi'an Jiaotong Univ), K. Hattar (SNL), A. Misra (Univ of Michigan)

3D Study of Neutron Irradiation Effects on Tensile Deformation in Fe-Based Alloys using High Energy Synchrotron X-Rays

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

Recent Advances in Analytical Electron Microscopy for Irradiated Materials

Chad M. Parish, Philip D. Edmondson, Kevin G. Field, Kurt A. Terrani (ORNL), Rachel L. Seibert (IIT), Yutai Katoh (ORNL)

Development of Ultra Small Scale Mechanical Testing and Localized He Implantation for Nuclear Applications

P. Hosemann, H. Vo, A. Reichardt, D. Frazer, Z. Wang, C. Howard (Univ of California, Berkeley)

Applications of Transient Grating Spectroscopy to Radiation Materials Science

Cody Dennett, Sara Ferry, Penghui Cao (MIT), Shie-Hong Lin, Ji-Jung Kai (City Univ of Hong Kong), Michael Short (MIT)

Poster Session

Corrosion Behavior of Pressurized Austenitic Tubes in Oxygen Containing PbBi at 550°C

A. Weisenburger, A. Heinzel, G. Müller (KIT)

Dependencies of Alpha Embrittlement in Neutron-Irradiated Model Fe-Cr-Al Alloys

S. A. Briggs (Univ of Wisconsin, Madison), P. D. Edmondson, K. C. Littrell (ORNL), Y. Yamamoto (ORNL UT-Battelle), K. Sridharan (Univ of Wisconsin, Madison), K. G. Field (ORNL)

In Situ TEM Microcompression Pillar Size Effects in Fe-9Cr ODS

K. H. Yano, M. J. Swenson, J. P. Wharry (Boise State Univ)

In Situ Sample Environment for Studying Corrosion of Nuclear Materials

Mohamed Elbakhshwan, Simerjeet Gill (BNL), Arthur Motta (Penn State), Randy Weidner, Thomas Anderson, Lynne Ecker (BNL)

Effect of Alloying Additions on Wrought FeCrAl Alloys for Accident-Tolerant Fuel Cladding

Yukinori Yamamoto (ORNL UT-Battelle), Kevin G. Field, Bruce A. Pint, Kurt A. Terrani (ORNL)

Recovery and Recrystallization Behavior of Nb-Containing Fe-Cr-Al Alloys

Zhiqian Sun (ORNL), Yukinori Yamamoto (ORNL UT-Battelle)

Mechanical and Microstructural Characterization of Low-Temperature Neutron Irradiated Zircaloy-4

Chinthaka M. Silva, Keith J. Leonard, Josina W. Geringer (ORNL), Eric Van Abel (2SHINE Medical Technologies), Christopher Bryan (ORNL)

TEM Study of Zircaloy 2 with FeCrAl Layer under Simulated BWR Environment, Donghee Park

Peter A. Mouche, Weicheng Zhong, Xiaochun Han, Brent J. Heuser (Univ of Illinois), Kiran K. Mandapaka, Gary S. Was (Univ of Michigan)

Alternative Fabrication of Volatile Metal Fuel Slugs for Sodium-Cooled Fast Reactor

Ki-Hwan Kim, Jong-Hwan Kim, Hoon Song, Seok-Jin Oh, Chan-Bock Lee (KAERI)

Spatially Resolved Thermal Transport Measurements in Graphite Coated Fuel Particles

David H. Hurley (INL), D. V. Rao, Erik P. Luther, Igor O. Usov, Miles F. Beaux, (LANL), Brycen L. Wendt (Idaho State), Yuzhou Wang, Marat Khafizov (Ohio State)

Distillation of Americium from Plutonium Americium Oxide

Leah Squires, Paul Lessing (INL)

Fabrication of Minor Actinide MOX Fuel for the AFC-2C and -2D Irradiations

Stewart Voit, Stephen Willson, Kenneth McClellan (LANL)

Identification and Quantification of Carbon Phases in Conversion Fuel for the Transient Reactor Test Facility

Robert Steele, Angelica Mata, Mary Lou Dunzik-Gougar (Idaho State Univ), Isabella van Rooyen (INL)

Microstructural Characteristics of U-Zr Ingot Slug and Atomized Powder for SFR Metal Fuel

S. J. Oh, S. W. Kuk, H. J. Jun, J. H. Kim, K. H. Kim (KAERI)

Orientation-Dependent Surface Faceting in UO₂

Yinbin Miao (Univ of Illinois), Kun Mo, Jeffrey Fortner, Ruqing Xu, Laura M. Jamison, Abdellatif M. Yacout (ANL), Tiankai Yao, Jie Lian (RPI) (ANL)

An Introduction to the FCRD Transmutation Fuels Handbook 2015

Dawn E. Janney, Cynthia A. Papesch (INL)

Oxygen Potential Measurement and Point Defect Chemistry of UO₂

Masashi Watanabe, Masato Kato (JAEA), Takeo Sunaoshi (Inspection Development Co.)

Characterization of Fresh Nuclear Fuel using Time-Of-Flight Neutrons

Adrian Simon Losko (Univ of California, Berkeley), Sven Vogel, Mark Andrew Bourke (LANL), Anton Tremsin (Univ of California, Berkeley), Stewart L. Voit, Kenneth J. McClellan, Michael Mocko, Peter Hosemann (Univ of California, Berkeley), Darrin D. Byler (LANL)

Nanoscale Mechanical Behavior of Nuclear Materials

U. Carvajal-Nunez, S. Pathak (Univ of Nevada, Reno), Y. Wang, N.A. Mara, J. T. White, E. S. Wood, A.T. Nelson (LANL)

Synthesis of ThN using a Carbothermic Reduction to Nitridation Process

A.J. Parkison, A.T. Nelson (LANL)

Fabrication of UN Microsphere Kernels for Fully Ceramic Microencapsulated Fuel

J. W. McMurray, T. B. Lindemer, R. D. Hunt, J. L. Collins, C. M. Silva, J. J. Henry, K. A. Terrani (ORNL)

Chromium-Based Mitigation Coatings on SiC Materials for Fuel Cladding

Caen Ang, Yutai Katoh, C. Kemery, J. Kiggans, Kurt Terrani (ORNL)

Fabrication and Testing of Complex Silicon Carbide Composite Structures

Hesham E. Khalifa, Chunghao P. Shih, George M. Jacobsen, Christian P. Deck (General Atomics)

Synchrotron Microdiffraction Study of Heavy-Ion-Irradiated Uranium-Molybdenum Dispersion Fuel

Laura Jamison, Kun Mo, Yinbin Miao, Bei Ye (ANL), Sumit Bhattacharya (Northwestern Univ), Ruqing Xu, Abdellatif M. Yacout (ANL)

Microstructural Characterization of In-Reactor Corrosion Tested Hastelloy N^® and 316 Stainless Steel

G Zheng, David Carpenter, M. Ames, Y. Ostrovsky, Gordon E. Kohse, Kaichao Sun, Lin-wen Hu (MIT)

Positron Annihilation Spectroscopy Investigation of Vacancy Clusters in Neutron-Irradiated 3C-SiC

Xunxiang Hu, Takaaki Koyanagi, Yutai Katoh (ORNL)

Multiscale Model for Simulating Fission-Induced Recrystallization in U-Mo Alloy

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

Comparison of Ion and Neutron Irradiations to 3 dpa at 500C in Ferritic-Martensitic Alloys

Matthew J. Swenson, Janelle P. Wharry (Boise State Univ)

First-Principles Study of Inert Gas Incorporation and Migration Zirconium Nitride

Zhi-Gang Mei, Abdellatif M. Yacout, Yeon Soo Kim, Gerard L. Hofman (ANL)

Neutron Irradiation Effects on the Graphitic Structure of a Fine-Grain Graphite

A. A. Campbell (ORNL), K. Takizawa (Tokai Carbon Co., Ltd.), E. Cakmak, Y. Katoh (ORNL)

In-Situ High Energy X-Ray Characterization of Tensile Deformation of Advanced Austenitic Stainless Steels

Chi Xu (ANL/Univ of Florida), Xuan Zhang, Meimei Li, Jun-sang Park, Peter Kenesei, Jonathan Almer (ANL), Yong Yang (Univ of Florida)

Radiation Tolerance of Silicon Carbide Joints at LWR Relevant Temperature

Takaaki Koyanagi, Yutai Katoh, James O. Kiggans (ORNL), Tatsuya Hinoki (Kyoto Univ), Christina A. Back (General Atomics)

Development of Surface Grain Relief on Self-Ion Irradiated Copper

Cody A. Dennett, Michael Short, Alejandro Vega-Flick, Alexei A. Maznev, Keith A. Nelson (MIT)

Microstructure Evolution in Ion-Irradiated of UO₂

Lingfeng He, Jian Gan, Todd R. Allen (INL)

Advanced Characterization of Fuel Pellet and Cladding from the HB Robinson NPP

Philip D. Edmondson, Chad M. Parish, Tyler Gerczak, Kurt A. Terrani (ORNL)

Summary of FUTURIX-FTA Non-Destructive Examination

Heather J. M. Chichester, Jason M. Harp (INL)

Materials Irradiation Facility (MIF) at the High Flux Isotope Reactor (HFIR)

Nesrin O. Cetiner, Graydon L. Yoder, Joel L. McDuffee, Don Wilder, Young So Kwon, Chris Bryan (ORNL)

Topological Defects in Graphite under Irradiation using Molecular Dynamics

Anant Raj, Jacob Eapen (NCSU)

An Improved Methodology to Determine Pore Size Distribution and Pore Density in the High Burnup Structure

F. Cappia, V. V. Rondinella (EC-JRC-ITU)

Microstructural Characterization of Irradiated Fuels and Materials for the United States High Performance Research Reactor Fuel Development Program and the Fuel Cycle Research and Development Program

Bjorn E. Westman, Julie Tucker (Oregon State Univ), Brandon D. Miller (INL)

Fiber Optic Instrumentation in High Temperature Irradiation Environments

Christian M. Petrie (ORNL)

Updated Phase Calculation Method for Metallic Nuclear Fuel in BISON

Christopher Matthews, Jack Galloway, Cetin Unal (LANL)

Thermal Transport at (001) Twist Grain Boundaries in UO₂

A. Chernatynskiy (Missouri Science and Technology Univ), B. Deng (Montana Tech of the Univ of Montana), S. Phillpot (Univ of Florida)

Neutronics Analysis Supporting Baseline Fuel-Rodlet Irradiation Design in TREAT Multi-SERTTA Vehicle

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

Mechanical Analysis to Study Pore Formation Mechanism in U-Mo/Al Dispersion Fuel

Gwan Yoon Jeong (UNIST), Yeon Soo Kim (ANL), Kyu Hong Lee (KAERI), Dong-Seong Sohn (UNIST)

Investigating Accident Tolerant Fuel Concepts using the BISON Fuel Performance Code

Kyle A. Gamble, Jason D. Hales (INL)

MARMOT Modeling of Microstructure-Dependent Thermal Conductivity in Nuclear Fuels

Xianming Bai (INL), Michael R. Tonks (INL/Penn State), Yongfeng Zhang, Jason D. Hales (INL)

An Interface Debonding Model for Integrity Assessment of Nuclear Fuel Rods

Ruijie Liu (UT San Antonio)

Fuel Performance Simulation of FeCrAl Cladding during Steady-State LWR Operation

R. Sweet (Univ of Tennessee), K. Terrani (ORNL), B. D. Wirth (Univ of Tennessee)

Comparison of Subdivided Versus Full-Length Fuel Pin Burnup in the ATF-2 Safety Analysis

Wilson M. Cowherd (INL)

Effect of Reactor Radiation on the Thermal Conductivity of Graphite-Based Dispersion Fuel

Kun Mo, Yinbin Miao, Arthur E. Wright, Dimitrios C. Kontogeorgakos, Heather M. Connaway, Abdellatif M. Yacout (ANL)

String-Like Transport in Superionic Conductors

Ajay Annamareddy, Jacob Eapen (NCSU)

A Preliminary Overview of Metal Fuel Models in BISON

S.R. Novascone, P. Medvedev, K. A. Gamble, R. J. Gardner, A. X. Zabriske (INL)

Continuum Scale Modeling of Thermal Conductivity in Hyperstoichiometric Uranium Dioxide

Austin W. Travis (Univ of California/LANL), David A. Andersson, Andrew T. Nelson (LANL)

Ab Initio Molecular Dynamics Analysis of Xenon Incorporation in Uranium Dioxide

C. A. Manring, J. L. Wormald, A. I. Hawari (NCSU)

Analysis of a Loop for Fission Gas Release and Monitoring at the PULSTAR Reactor

A. I. Hawari, M. Liu, M. R. Smith (NCSU), J. M. Harp, G. Pastore, R. L. Williamson (INL)

Preliminary Compendium of the Initial Conditions and Evolution of the Fundamental Interactions of SiC with Ag and Pd

Daniel Velázquez, Rachel Seibert, William Limestall, Jeff Terry (Illinois Inst of Technology)

Study on Modeling of Nuclear Fuel End Drop during a Hypothetical Accident

Huan Li, Hernando Candra, Jose Pires (NRC)

Synchrotron Characterization of the Oxidation of Advanced Steel Cladding Alloys

Mohamed Elbakhshwan, Simerjeet Gill, Abdul Rumaiz (BNL), Raul Rebak (General Electric), Lynne Ecker (BNL)

First-Principles Study of Surface Properties of U₃Si₂ for Accident Tolerant Fuel

Zhigang Mei, Abdellatif M. Yacout, Yinbin Miao (ANL), David Andersson (LANL)

Pool Boiling CHF Experiment for Cr-Alloy-Coated Accident Tolerant Fuel Cladding

Chan Lee, Chang Hwan Shin, Wang Kee In (KAERI)

Characterization of Simulated BWR and Steam Exposed FeCrAl Coated Zircaloy 2

Peter A. Mouche, Weicheng Zhong, Brent J. Heuser (Univ of Illinois), Kiran K. Mandapaka, Gary S. Was (Univ of Michigan)

Enhanced Thermal Conductivity UO₂-BeO and UO₂-SiC Fuels Behavior

Rong Liu, Wenzhong Zhou (City Univ of Hong Kong)

Advanced Structural Materials and Radiation Damage-I

Towards High Performance Oxide-Dispersion-Strengthened Alloys

Tianyi Chen, Hyosim Kim, Jonthan Gigax, Eda Aydogan, S. Ukai, Frank Garner, Lin Shao (Texas A&M)

Processing of Nanostructured Ferritic Alloys for Advanced Reactor Core Materials

S. A. Maloy, E. Aydogan, O. A. Anderoglu, T. A. Saleh (LANL), G. R. Odette (Univ of California, Santa Barbara), D. Hoelzer (ORNL), J. J. Lewandowski (CWRU), C. Lavender (PNNL), M. B. Toloczko, T. S. Byun (PNNL), T. Leonhardt (Rhenium Alloys)

Chemical Complexity Controls Energy Dissipation and Defect Evolution

Y. Zhang, G. M. Stocks, K. Jin, H. Bei (ORNL), C. Lu, L. Wang (Univ of Michigan), B. C. Sales, L. K. Beland, R. E.Stoller (ORNL), W. J. Weber (Univ of Tennessee)

Radiation Effects in Innovative Structural Materials

S. J. Zinkle (Univ of Tennessee), C. K. Ang, N. A. P. Kiran Kumar (ORNL), C. Li, J. Brechtl (Univ of Tennessee), H. Bei (ORNL)

Accelerated Ion Irradiation for Emulation of In-Reactor Radiation Damage

G. S. Was (Univ of Michigan), A. Motta (Penn State), B. Wirth (Univ of Tennessee)

Advanced Structural Materials and Radiation Damage-II

Dispersion of Nano-Sized Oxide Particles in Ni-based Alloy

Jinsung Jang, Young-Bum Chun, Suk Hoon Kang, Xiaodong Mao, Seongsu Lee, Ki Myung Song, Kunok Chang, Chang-Kyu Rhee (KAERI)

A Radial Heat Flow Apparatus for Thermal Conductivity Characterisation of Cylindrical Samples

Loïc Fave, Manuel A. Pouchon (Paul Scherrer Inst)

Additive Manufacturing of Research Reactor Control Elements and Subsequent Neutron Irradiation

Kurt A. Terrani, James Kiggans (ORNL), Niyanth Sridharan (Univ of Tennessee), Maxim Gussev (ORNL), Mark Norfolk (Fabrisonic LLC), Joseph R. Burns (Georgia Tech), David Chandler (UT-Battelle, ORNL), S. Suresh Babu (Univ of Tennessee), Christopher Bryan, Daniel Pinkston (ORNL)

Irradiation in the Swiss Spallation Neutron Source and its Applications

Yong Dai, Manuel A. Pouchon (Scherrer Inst)

Corrosion of Candidate Materials in Molten FLiBe Salt for Fluoride-Salt-Cooled High-Temperature Reactor (FHR)

Guoping Cao (Univ of Wisconsin-Madison), Guiqiu Zheng (MIT), Kumar Sridharan (Univ of Wisconsin, Madison)

NSUF Special Session-I

Overview of the U.S. Nuclear Science User Facilities

J. Rory Kennedy (INL)

Materials Characterization using the Facilities of the Center for Synchrotron Radiation Research and Instrumentation (CSRRI), A NSUF Partner Facility

Jeff Terry (Illinois Inst of Technology)

MAX Phases for the Nuclear Industry: Possibilities and Pitfalls

Michel W. Barsoum, Darin J. Tallman (Drexel Univ), Lingfeng He, Jian Gan (INL)

Initial Results from the High Fluence UCSB ATR-2 Irradiation

G. Robert Odette, Takuya Yamamoto, Peter Wells, Nathan Almirall (Univ of California, Santa Barbara), Randy Nanstad (ORNL), Keith Wilford, Tim Williams (Rolls-Royce)

Research and Development Capabilities Available through the Nuclear Science User Facilities

Brenden J. Heidrich (INL)

NSUF Special Session-II

The Role of Electron and Atom Probe Tomography in Characterization of Nuclear Fuels

Assel Aitkaliyeva, Cynthia Papesch (INL), Yaqiao Wu (Boise State Univ/Center for Advanced Energy Studies), Haiming Wen (Idaho State Univ)

Testing of LWR Surveillance Materials from the High Fluence UCSB ATR-2 Irradiation

Randy Nanstad (ORNL), Janet Robertson, Mikhail A. Sokolov (ORNL), G. Robert Odette, Takuya Yamamoto, Peter B. Wells, Nathan Almirall (Univ of California, Santa Barbara), William L. Server (ATI Consulting), Timothy Hardin (EPRI), Keith Wilford, Tim Williams (Rolls Royce)

Effect of Irradiation on Strengthening of a Model Fe-9Cr Oxide Dispersion Strengthened Alloy

J. P. Wharry, M. J. Swenson, C. K. Dolph, K. H. Yano (Boise State Univ)

High Energy X-Ray Applications for the Characterization of Metallic Uranium Alloys

Maria A. Okuniewski (Purdue Univ), Lynne E. Ecker, Mohamed Elbakhshwan, David Sprouster (BNL), Daniel Velazquez, Rachel L. Seibert, Daniel Lee, Jeff H. Terry (IIT), Yongho Sohn (Univ of Central Florida), Brandon D. Miller, Randall S. Fielding (INL)

Investigation of Fission Product Interaction with the SiC Containment Layer of High Burnup TRISO Fuel Particles

Rachel L. Seibert (IIT), Chad Parish, Kurt Terrani (ORNL), Jeff Terry (IIT)

Modeling and Simulation-II

Mechanical and Thermal Properties of Irradiated SiC/SiC Composites: Bridge Continuum Models with Atomic-Level Simulations

Fei Gao (Univ of Michigan), Ba Nghiep Nguyen, Charles H. Henager Jr. (PNNL)

Multiscale Investigation of Thermal Transport in UO₂ Fuel using Modeling and Simulation,

Michael Tonks (Penn State), Xiang-Yang Liu, David Andersson, Christopher Stanek (LANL), Aleksandr Chernatynskiy (Missouri Univ Sci Tech)

CAMPUS: Fully Coupled Multiphysics Modeling and Simulation of LWR and FBR Nuclear Fuel Behavior

Rong Liu, Wenzhong Zhou (City Univ of Hong Kong)

Physics-Based Modeling of Precipitation in Nuclear Structural Materials

Mahmood Mamivand, Huibin Ke (Univ of Wisconsin, Madison), G. Robert Odette (Univ of California, Santa Barbara), Dane Morgan (Univ of Wisconsin, Madison)

Advanced Fuels and Fuel Cycle-II

Tailored Microstructure and Properties in UO₂

Jie Lian, Tiankai Yao (RPI)

The Impact of Furnace-Testing on the Microstructure of an Irradiated U-Mo Fuel Plate

Dennis D. Keiser, Jian Gan, Jan-Fong Jue, Brandon D. Miller, Adam B. Robinson, James Madden, Francine Rice (INL)

Synthesis and Characterisation of Nanostructured UO₂ Compacts for Separate Effect Investigations

V. Tyrpekl, J. F. Vigier, T. Wiss, R. Jovani Abril, M. Cologna, J. Somers (JRC-ITE)

Small-Angle Neutron Scattering Measurements of the Delta Deuteride Phase in Zircaloy 4

Brent J. Heuser, Jun-li Lin (Univ of Illinois)

TEM Characterization of U-Mo Irradiated with High-Energy Xe Ions

Bei Ye, Laura M. Jamison (ANL), Sumit Bhattacharya (Northwestern Univ), Abdellatif Yacout (ANL)