Annual Meeting 2014 / Volume 110

ANS Officer

Meeting Officials, National Program Committee

Full Issue

Opening Plenary: “The U.S. Influence in the Global Nuclear Enterprise—I”

ANS President’s Special Session

“Special Session” Global Seismic Safety Issues After the Fukushima Daiichi Accident: On Identification and Treatment of Uncertainty About Seismic Issues—Practical Approach to Uncertainties of Seismic Issues and Availability of PRA

ANS General Chairman Chair Special Session: “The U.S. Influence in the Global Nuclear Enterprise—II”

ANS Technical Program Chair’s Special Session

Focus on Communications: Communicating with Communities–Panel

Focus on Communications: Building Policy Maker Support for Nuclear Facilities–Panel

Cyber Security in the Nuclear Age–Panel

University Infrastructure Needs–Panel

Education, Training, and Workforce Development: General

Development of the Graduate Certificate Program in Nuclear Security and Safeguards at UNLV

Alexander Barzilov, Denis Beller, William Culbreth (Univ of Nevada, Las Vegas)

Online Multidisciplinary Nuclear Power Generation Graduate Certificate Program

Keith E. Holbert (Arizona State Univ)

Use of a Sub-Scale, See-Through PWR Operating Model for Nuclear Energy Engineering Education

T. P. Filburn, J. K. Smith (Univ of Hartford), R. A. Matzie (RAMatzie Nuc Tech Consulting), C. C. Yavuzturk (Univ of Hartford)

Nuclear Safety and Security Human Resource Development

Oum Keltoum Bouhelal (National School of Mineral Industry)

Future Needs for Generation IV Reactors Education and Training

Petre Ghitescu, Gabriel Lazaro Pavel (Univ “Politehnica” of Bucharest)

Virtual Verification Method for China Lead-Alloy Cooled Research Reactor Refueling System

Jinbo Zhao, Tao He, Zhihui Yang, Meihua Zeng, Yunqing Bai, Pengcheng Long (Chinese Academy of Sciences/Univ of Science and Technology of China)

SRS Plutonium Disposition Project Update–Panel

Advanced Fuel Cycle Technology: Special Session in Honor of Dr. Michael Lineberry

Modified Fabrication Method of Metal Fuel Slug for Preventing Evaporation of Volatile Elements

Ki-Hwan Kim, Jong-Hwan Kim, Hoon Song, Hyung-Tae Kim, Chan-Bock Lee (KAERI)

An Efficient Electrorefining Mass Transport Model for Pyroprocessing Simulation

Riley M. Cumberland, Man-Sung Yim (KAIST)

Transient Testing Plan for Accident Tolerant Fuels Program

D. M. Wachs, N. Woolstenhulme (INL)

An Earthquake Modeling Result of a Pyroprocessed Waste Repository

Youn-Myoung Lee, Jongtae Jeong (KAERI)

Three-Level Fuel-Cycle Strategy to Improve Fast Reactor Economics and Non-Proliferation Characteristics

Charles Forsberg (MIT)

Effects of BeO Thermal Conductivity Degradation on LWR UO₂-BeO Fuel Performance

Yanin Sukjai, Alexander Mieloszyk, Mujid S. Kazimi (MIT)

Commercial-Scale Pyroprocessing Failure Modes and Implications for Operations and Safeguards

Robert O. Hoover, Philip L. Lafreniere, Edward D. Blandford (Univ of New Mexico)

Experiments in Used Fuel Disposition, Storage, Transport, and Disposal

Potential Effect of Interfacial Bonding on Used Nuclear Fuel Vibration Reliability

Jy-An Wang, Hao Jiang, Hong Wang (ORNL)

Passive Optical Impurity Monitoring of Dry Storage Containers for Spent Fuel

Ryan M. Meyer, Andrew M. Casella, Jonathan D. Suter, Hong Qiao, Norm C. Anheier (PNNL), Mark A. Prelas (Univ of Missouri-Columbia)

Surrogate Spent Nuclear Fuel Vibration Integrity Investigation

Jy-An Wang, Hong Wang, Bruce Bevard, Robert Howard (ORNL), Michelle Flanagan, Gordon Bjorkman (NRC)

Recycle and Reuse of Components from Used Nuclear Fuel

Future Recycle of Used Nuclear Fuel in the United States—Resolution of Issues

Emory D. Collins, G. D. Del Cul (ORNL)

Management of Recycled/Reprocessed Uranium

Paul Murray, Sven Bader (AREVA)

Zeolite Membranes for the Separation of Radioactive Krypton and Xenon

Philip Crawford (Georgia Tech), Ramesh Bhave (ORNL), Sankar Nair (Georgia Tech)

Options for a Sustainable MOX Fuel Cycle in PWRs for Rapid Utilization of Recycled Plutonium

Michael A. Perlin, Alexey I. Soldatov, Andrew C. Klein (Oregon State Univ)

Maximizing the Value of the U.S. Depleted Uranium Inventory

Urairisa Phathanapirom, Erich Schneider (Univ of Texas at Austin)

Fuel Cycle Simulators and Systems Analysis

Expert Elicitation of Across-Technology Correlations for Reactor Capital Costs

Erich Schneider (Univ of Texas at Austin), Brent Dixon (INL), Francesco Ganda (ANL), T. Jay Harrison (ORNL), Ed Hoffman (ANL), Kent Williams (Consultant), Thomas Wood (PNNL)

Fully Coupled Temperature Distribution, Plutonium and Oxygen Diffusion Simulation in (U, Pu)O₂ Fuels

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

Hybrid Energy: Combining Nuclear and Other Energy Sources

Challenges for Zero-Carbon Nuclear-Renewable Energy Futures

C. W. Forsberg, M. Golay (MIT)

Increasing Baseload Light-Water Reactor Revenue with Heat Storage and Variable Electricity Output

C. W. Forsberg (MIT), E. Schneider (Univ of Texas at Austin)

Plutonium Disposition Alternatives–Panel

Fuel Cycle and Waste Management: General—I

High-Level Nuclear Waste Redefined

James Conca (UFA Ventures)

Surrogate Alloy Waste Components Impact on Composition and Corrosion

Luke Olson (Savannah River National Laboratory)

Influence of Boron Nitride Addition on Rod Internal Pressure of a High BU Fuel Rod

Gwan-yoon Jeong, Dong-seong Sohn (UNIST), Yong-sik Yang, Je-keun Bang (KAERI)

Protective Coatings of Melting Crucible for Metal Fuel Slugs

J. H. Kim, H. Song, Y. M. Ko, K. H. Kim, C. B. Lee (KAERI)

Fuel Cycle and Waste Management: General—II

A Comparison of Fuel Cycle Environmental Impact Estimates

Urairisa Phathanapirom, Erich Schneider, Margaret Flicker (Univ of Texas at Austin)

Unconventional Uranium Resources and Production Costs

Erich Schneider, Harry Lindner (Univ of Texas at Austin)

Simulation-based Investigation of Electric Power Generation by Using Gamma Radiation from Spent Nuclear Fuel

Hanoel Lee, Man-Sung Yim (KAIST)

Preliminary Evaluation of Several Multi-Stage, Thermal-Spectrum Thorium Fuel Cycles

Steven Krahn (Vanderbilt Univ), Andrew Worrall (ORNL), Allen Croff, Timothy Ault (Vanderbilt Univ)

Improving Inert Matrix Burnup Using a Linear Reactivity Model

David W. Harding (Univ of Texas at Austin), Geoffrey Recktenwald (Michigan State Univ), Mark Deinert (Univ of Texas at Austin)

ACRSP Contributions to Actinide Chemistry in Brine under Subsurface Conditions

J. F. Lucchini, D. Cleveland, J. Swanson, M. K. Richmann, D. T. Reed (LANL)

Human Factors, Instrumentation, and Controls: General

Estimation Method of Loss of Situation Awareness due to Automation in Nuclear Power Plants (NPPs)

Seung Min Lee, Ho Bin Yim, Poong Hyun Seong (KAIST)

Digital Systems Testability in the Context of Diversity

Steven A. Arndt (U.S. NRC)

Human Factors Engineering Training Materials for the Nuclear Industry

Joseph Naser (EPRI), Lewis Hanes (Independent Research Consultant), Robert Fink (CDF Services)

An Investigation into Causality of Operators’ Noncompliance during EOP Simulation

Sun Yeong Choi, Wondea Jung (KAERI)

Evaluation of the Time-Dependent Issues of Natural Circulation SMR Primary Circuit Parameters Definition for Design of Operational Procedures and Reactor Control Algorithms

Alexey Rezvoi (NuCon. US), Alexey I. Soldatov (Oregon State Univ)

Isotopes and Radiation: General

TCAD Simulation of Charge Collection in GaN Schottky Diode Radiation Detector

Jinghui Wang, Padhraic L. Mulligan, Lei R. Cao (Ohio State Univ)

Neutron-Gamma Separation in a Gadolinium Based Semiconductor Neutron Detector

Praneeth Kandlakunta (Ohio State Univ/MP Machinery & Testing), Lei R. Cao (Ohio State Univ)

Development of a Semi-Automated Testing and Calibration System for Custom-Built TPC DAQ Hardware

Brycen L. Wendt, Eric A. Burgett (Idaho State Univ)

Simulation of Ni-63 Nuclear Micro Battery Using Monte Carlo Modeling

Tae Ho Kim, Ji Hyun Kim (UNIST)

An Investigation of a Logging Tool Based on Various Neutron Sources and Detectors for Measurements of Porosity and Density

Kyoung O. Lee (NCSU), Avneet Sood (LANL), Adan F. Calderón, Robin P. Gardner (NCSU)

Measurements of Fast Neutron Flux using an Array of EJ-299-33A Scintillator Detectors

Alexander Barzilov, Jessica Hartman, Norman Richardson (Univ of Nevada, Las Vegas)

Current Issues in Computational Methods—Roundtable: Computational Human Phantoms

Uncertainty Quantification and Sensitivity Analysis Method

Uncertainty Quantification for Coupled Monte Carlo and Thermal-Hydraulics Codes

Xu Wu, Tomasz Kozlowski (Univ of Illinois at Urbana-Champaign)

Employing Non-Converged Iterates for Reduced Order Modeling Basis Construction

Bassam A. Khuwaileh, Youngsuk Bang, Congjian Wang, Hany S. Abdel-Khalik (NCSU)

Propagation of Error Bounds due to Active Subspace Reduction

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

Transport Methods and Mathematical Modeling

Comparison of Iterative Time-Eigenvalue Methods with Discrete Ordinates and Monte Carlo

Brian C. Kiedrowski (LANL)

Comparison of Prompt Kinetics Models Derived from Alternate Eigenvalues

Brian C. Kiedrowski (LANL)

Mesh Generation for Transport Sweeps Using a Piece-Wise Linear Discontinuous Discretization

Tarek Ghaddar (Univ of Michigan), Jean C. Ragusa (TAMU)

Acceleration of SN Power Iteration with Coarse Mesh Formulation Employing Angular Flux Discontinuity Factors

Chae Ho Lim, Han Gyu Joo (Seoul National Univ)

Improved Monte Carlo Tallying of Multi-Group Scattering Moment Matrices

Adam G. Nelson, William R. Martin (Univ of Michigan)

Geometry Navigation Acceleration Algorithm for Monte Carlo Radiation Simulation

Bin Wu (Chinese Academy of Sciences), Zhenping Chen, Jing Song (Chinese Academy of Sciences/Univ of Science and Technology of China), FDS Team

Computational Methods: General

ICE-Based Preconditioning Method for Euler Equations

Ling Zou, Haihua Zhao, Hongbin Zhang (INL)

Development of Quasi-Static Dynamic Simulation Capability in Monte Carlo Code RMC

Xu Qi, Wang Kan (Tsinghua Univ)

A Temperature Dependence Study of Alpha/Beta Cumulative Distribution Functions Based on S(α,β) Data

Andrew T. Pavlou, Wei Ji (RPI)

Energy Expansion in Response Matrix Methods Using the Karhunen-Loève Transform

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

A New Importance Measure for Reduced Order Modeling

Bassam A. Khuwaileh, Hany S. Abdel-Khalik (NCSU)

Subspace Methods for Multi-physics Reduced Order Modeling in Nuclear Engineering Applications

Bassam A. Khuwaileh, Hany S. Abdel-Khalik (NCSU)

Data, Analysis, and Operations for Nuclear Criticality Safety

A Systems Engineering Approach for Implementing ANSI/ANS-8 Standards for CAAS and EP&R

Peter L. Angelo (Y-12 Natl Security Complex)

COG Validation for Lead and Polyethylene Reflected SILENE Criticality Excursion Benchmark Experiments

Soon Sam Kim, David Heinrichs, Rich Buck, Ed Lent, Chuck Lee (LLNL)

Comparison of Bounding and Realistic Models to Subcritical Measurements

J. Hutchinson, M. Mitchell, T. Cutler (LANL), J. Alwin (PNNL)

Neutron Transmission Correction using Multiplicity Analysis

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

Unusual Behaviors Resulting from Unusual Control Schemes in Criticality Safety

Theresa E. Cutler, Mark V. Mitchell, Jesson D. Hutchinson (LANL)

ANS Nuclear Criticality Safety Division (NCSD) Session in Memory of Richard (Dick) McKnight

ICSBEP Criticality Calculations with ENDF/B-VII.1 Cross Sections

A. C. Kahler, R. E. MacFarlane (LANL)

Three Analytic Benchmarks in COG

Edward M. Lent (LLNL)

Results for the Intermediate-Spectrum ZEUS Benchmark Obtained with New ^63,65Cu Cross-Section Evaluations

Vladimir Sobes, Luiz Leal (ORNL)

Revival of Criticality Safety Research in Japan Atomic Energy Agency

Kotaro Tonoike, Kazuhiko Izawa, Hiroki Sono, Miki Umeda, Yuichi Yamane (JAEA)

A Tribute to Richard D. McKnight

J. Blair Briggs (INL), Robert W. Schaefer (ANL/INL, retired)

Notes on Validation of Criticality Safety and Reactor Physics Calculations

Tatiana Ivanova (Institut de Radioprotection et de Sûreté Nucléaire)

Correlations of Error Sources and Associated Reactivity Influences

Dennis Mennerdahl (E M Systems)

Critical and Subcritical Experiments

Historical Critical Experiments

Richard E. Malenfant (LANL, retired)

Benchmark Specifications and Results for β_eff in a HEU Metal System Using ORSphere

Margaret A. Marshall, John D. Bess (INL)

Prompt Neutron Decay Constants in a Highly Enriched Uranium Copper Reflected System

George McKenzie, Travis Grove, Rene Sanchez, John Bounds (LANL)

Characterization of the NPOD3 Detectors in MCNP5 and MCNP6

Kimberly Clark, Jesson Hutchinson, Avneet Sood (LANL)

Joint LANL/CEA Measurements on Godiva IV

J. Hutchinson, M. Smith-Nelson, A. Sood, J. Goda, J. Bounds, T. Cutler (LANL), A. Chapelle, P. Casoli (CEA)

Investigation of k_eff Versus Fraction of Critical Mass

J. Hutchinson, T. Cutler, R. Sanchez, M. Mitchell, D. Hayes (LANL)

Application of Performance Metrics in Assessing the LLNL Nuclear Criticality Safety Program

David Heinrichs, Song Huang (LLNL), Mark Lee (DOE/NNSA)

Criticality Safety Program Metrics–Paper/Panel

ANS 8 Standards Forum

Fuel Cladding Behavior Under Accident Conditions

The Turbine Trip without Bypass Analysis of Kuosheng BWR/6 Using TRACE/FRAPCON/FRPATRAN

H. C. Chang, W. K. Lin, W. Y. Li, C. Shih (Tsinghua Univ), J. R. Wang, H. T. Lin (Atomic Energy Council)

The Spent Fuel Pool Analysis of Chinshan BWR/4 using TRACE/CFD/FRAPTRAN

C. Shih, W. Y. Li, H. C. Chang (Tsinghua Univ), J. R. Wang (Atomic Energy Council), W. K. Lin, Y. S. Tseng, (Tsinghua Univ), H. T. Lin (Atomic Energy Council)

Historical Review of Fuel Fragmentation and Dispersal Observations in Design Basis Loss-of-Coolant Accident Testing

P. Raynaud, M. Flanagan (NRC)

Influence of Burnup on Fuel Rod Characteristics, and Implications for Loss-of-Coolant-Accident Behavior

M. Flanagan (NRC)

Round Table on Organizing Special Sessions for ANS Meetings–Workshop

Current Topics in Probabilistic Risk Analysis

Branch-and-Bound Algorithm Applied to Discrete Dynamic Event Trees

Joseph Nielsen (INL), Akira Tokuhiro, Robert E. Hiromoto (Univ of Idaho)

Event Tree Success Branch Modeling Approaches in SAPHIRE/SPAR

Zhegang Ma, John Schroeder (INL)

Comparison of MELCOR and SAS4a for Dynamic Event Simulations

M. R. Denman, J. N. Cardoni, T. A. Wheeler (SNL)

Introduction of Supervised Learning Capabilities of the RAVEN Code for Limit Surface Analysis

Cristian Rabiti, Diego Mandelli, Andrea Alfonsi, Joshua Cogliati, Robert Kinoshita (INL)

Nuclear Installations Safety: General

Effect of Seasonal Meteorological Variations on Radioactive Plume Dispersion—A Segmented Gaussian Approach

Mazzammal Hussain (Intl Islamic Univ), Salah Ud-Din Khan (King Saud Univ), Waqar Adel Syed (Intl Islamic Univ)

The Analysis of Hydrogen Diffusion Behavior in Containment by Using GOTHIC Code and MAAP Code

Zhen-Yu Hung, Pin-Yu Yuan, Yuh-Ming Ferng, Wen-Sheng Hsu, Bau-Shei Pei (National Tsinghua Univ)

Safety Assessment of HANARO Research Reactor in Light of FDA

Hyungkyoo Kim, Jinwon Shin, Hoansung Jung (KAERI)

Feasibility of Reactor Emergency Power by Thermoelectric Waste Heat Recovery

Byeonghee Lee, Sung Won Lim, Young Jong Chung (KAERI)

Nevada National Security Site (NNSS): Role and Contributions to the Nonproliferation and Global Security Community–Panel

NNSA Graduate Program Past Experiences and Current Highlights–Panel

Human Reliability in Nuclear and Radiological Systems–Panel

Plutonium Disposition—The Clear and Present Danger, 20 Years Later–Panel

Proliferation Risk and Sustainability of Nuclear of Nuclear Energy Systems–Panel

Small Modular Reactor Developments–Panel

New Nuclear Construction Around the World–Panel

Advanced/Gen-IV Reactors

Efficiency of Nuclear and Conventional Air-Brayton Power Cycles

H. Andreades (Univ of California, Berkeley), C. W. Forsberg (MIT), P. F. Peterson (Univ of California, Berkeley)

A Comparison of a Recuperated Open Cycle (Air) Brayton Power Conversion System with the Traditional Steam Rankine Cycle for the Next Generation Nuclear Power Plant

Bahman Zohuri, Patrick McDaniel, Cassiano de Oliviera (Univ of New Mexico)

Market for Hot Air from Salt-Cooled Reactors with Air-Brayton Power Cycles

C. W. Forsberg (MIT)

Market Performance of the Mark 1 Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor

Daniel Curtis, Charles Forsberg (MIT)

Hybrid Molten Salt Reactor (HMSR) System Study

Robert D. Woolley (Princeton Univ), Laurence F. Miller (Univ of Tennessee)

Chemical Compatibility of Containment and Other Materials with FHR Coolant Salts

John D. Stempien, Ronald G. Ballinger, Charles W. Forsberg (MIT)

MSR On-line Reprocessing Technology and Nonproliferation Aspects

Jan Uhlíř (Research CentreŘež)

Study of Neutronic-Thermohydraulic Coupled Calculation of SCWR

Shichang Liu, Zeguang Li, Kan Wang (Tsinghua Univ)

Validation of AGREE with HTTR Control Rod Withdrawal Tests

Volkan Seker, Thomas J. Downar (Univ of Michigan)

Operations and Power: General

Correlation Between the Microstructure and Mechanical Properties of Irradiated Fe-9Cr ODS

M. Swenson, C. Dolph, J. Wharry (Boise State Univ)

Thermal Annealing of Reactor Pressure Vessels: International Experience and U.S. Perspective

Mikhail A. Sokolov, Randy K. Nanstad (ORNL), William Server (ATI Consulting)

Fukushima Lessons Learned Severe Accident Goals

James M. Gleason (GLSEQ), Oliver Fritz (SCHOTT AG Standort/Site), Claude Thibault (GLSEQ), Edward L. Quinn (ANS Past President)

Post-Fukushima Technology Enhancements to Improve Safety Margins–Paper/Panel

History and Current State of Radiation Detection—A Review Session in Honor of Professor Nick Tsoulfanidis

Confidence in LWR Instrumentation Data during a Severe Accident

Joy Rempe, Darrell Knudson (INL)

Climate Change, Scaling Up Nuclear Power, and Closing the Fuel Cycle: An Assessment of Kr-85 Atmospheric Dose

Glenn Sjoden, Michael Chin, Bojan Petrovic (Georgia Tech)

Large Area Zero Bias Solid-state Neutron Detectors

Yaron Danon, Rajendra Dahal, Kuan-Chih Huang, James J.-Q. Lu, Adam Weltz, Ishwara B. Bhat (RPI)

Gamma-Ray Detection: A Historical Overview

Sheldon Landsberger (Univ of Texas at Austin)

Polaris 3-D Position-Sensitive CdZnTe Gamma-Ray Imaging Spectrometers

Zhong He (Univ of Michigan)

A Brief History of Radiation Detectors for Homeland Security Applications

Raymond Klann (ANL)

Computational Tools for Radiation Protection and Shielding

MCNP6 Cosmic and Terrestrial Background Particle Fluxes—Release 4

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

Production of Energetic Light Fragments with Expanded Cascade Exciton Model (CEM)

Leslie M. Kerby (LANL/Univ of Idaho), Stepan G. Mashnik (LANL), Akira T. Tokuhiro (Univ of Idaho)

Analysis of the Scattering a Beam of Neutrons or Photons from Broad Rectangular Targets—Modeling and Compact Benchmark Tools for Quick Estimates and MC Verifications

E.V. Steinfelds, K. Andrew (Western Kentucky Univ)

Development of a Neutron Spectroscopy Unfolding Suite Integrating Former- and Next-Generation Codes

Brycen L. Wendt, Emerald D. Ryan, Eric A. Burgett (Idaho State Univ)

Establishment and Analysis of Mono-energy Photon Specific Absorbed Fractions of Rad-HUMAN Phantom Using Monte Carlo Method

Wen Wang (Chinese Academy of Science/Univ of Science and Technology of China), Mengyun Cheng, Pengcheng Long (Chinese Academy of Science), Yican Wu(Chinese Academy of Science/Univ of Science and Technology of China), FDS Team

Preliminary Analysis of Source Term for Primary Coolant System of China Lead-based Research Reactor (CLEAR-I)

Tongqiang Dang, Lanfang Mao, Haixia Wang, Qian Guo, Yican Wu, FDS Team (Chinese Academy of Science)

Testing of ARCHER-CT, A Fast Monte Carlo Code for CT Dose Calculation: Experiment versus Simulation

Tianyu Liu, Xining Du, Lin Su, Yiming Gao, Wei Ji (RPI), Da Zhang, Jim Q. Shi, Bob Liu, Mannudeep K. Kalra (Mass General Hospital), X. George Xu (RPI)

Radiation Protection and Shielding–Roundtable

Advanced Tallies in MCNP–Tutorial

Radiation Protection and Shielding: General

Computational Benchmarks for Minimizing the Legacy Problem in Oil Well Logging Source Replacement

Robin P. Gardner (NCSU), Avneet Sood (LANL), Kyoung O. Lee (NCSU)

Uranium and Plutonium Fission Product Gamma Intensity Measurements and MCNP6 Simulations

M. T. Andrews (Royal Military College of Canada), J. T. Goorley (LANL), E. C. Corcoran, D. G. Kelly (Royal Military College of Canada)

Three Dimensional Phase Space Investigation of Aqueously Grown Zinc Oxide

Austin Tam, Daniel Isaacs, Eric Burgett (Idaho State Univ)

Simulation of Electron Probe Microanalysis for the Purposes of Automated Material Identification—Initial Evaluation of Available Monte Carlo Tools

Thomas M. Miller, Bruce W. Patton, Charles F. Weber (ORNL)

Reactor Physics: General—I

Bias and Uncertainty Under-Prediction in MCNP6.1 Lattice Physics Calculations with Depletion

Alexander S. Bennett (Penn State Univ), Brian C. Kiedrowski, Forrest B. Brown (LANL)

CRANE: A Prototypic SCALE Module for Reduced Order Modeling

Ugur Mertyurek (ORNL), Congjian Wang, Youngsuk Bang, Hany Abdel-Khalik (NCSU)

Leakage-Corrected Discontinuity Factors for a Second-Generation Th-Pu Pressure-Tube SCWR

Katarzyna Carisse, Eleodor Nichita (Univ of Ontario Institute of Technology)

Prediction on Underestimation of Variance for Fission Rate Distribution in Monte-Carlo Calculation

Akio Yamamoto, Kotaro Sakata, Tomohiro Endo (Nagoya Univ)

Method of Characteristics Code Development at UNIST

Chidong Kong, Sooyoung Choi, Deokjung Lee (UNIST)

Reactor Physics: General—II

A Subgroup-Wavelet Coupling Method for Resonance Self-shielding Calculation

Liangzhi Cao, Lei He, Hongchun Wu (Xi’an Jiaotong Univ)

Feasibility of Nodal Equivalence Theory Using Functionalized Homogenized Parameters

Woosong Kim, Yonghee Kim (KAIST)

Stabilization of Monte Carlo Fission Source Distribution in p-CMFD Acceleration Method Compared to Fission Matrix Method

YuGwon Jo, Nam Zin Cho (KAIST)

An Improved CMFD Acceleration for SP3 Advanced Nodal Method

Tatsuya Sakamoto, Akio Yamamoto, Tomohiro Endo (Nagoya Univ)

Legendre Moments of the Neutron Free-Gas Scattering Kernel Using Gauss-Kronrod Quadrature

Matthew Gonzales, Anil K. Prinja (Univ of New Mexico), Brian Kiedrowski (LANL)

Reactor Physics: General—III

Verification of the DEFENS Code through the CANDU Initial Core Problem

Eun Hyun Ryu, Yong Mann Song (KAERI)

Validation of the WIMS9A/PARCS Code System for Power Density Calculations for the AP1000™ Reactor Core

Mohamed A. Elsawi, Amal S. Bin Hraiz (Khalifa Univ of Science, Technology and Research)

Application of Microscopic Depletion Correction in COSINE Core Analysis Code

Su Wang, Xiaoyu Hu, Yuhang Yan, Changhui Wang, Feng Shen, Yixue Chen (State Nuc Power Software Development Center)

Alternate Fast Neutron Burst Option with High-Flux, LEU-Based Neutron Source

Ross Radel, Eli Moll, David Ozburn (Phoenix Nuclear Labs), J. David Schneider (TechSource)

Reactor Physics: General—IV

WPEC SG38: Designing a New Format for Storing Nuclear Data

C. M. Mattoon, B. R. Beck (LLNL)

FUDGE: A Toolkit for Nuclear Data Management and Processing

B. R. Beck, C. M. Mattoon (LLNL)

Parameterized Representation of Macroscopic Cross Section for PWR Reactor Considering With 12 Burnable Absorber Fuel Rods in the Fuel Element

João Claudio B. Fiel (Military Institute of Engineering), Luiz Carlos Leal (ORNL)

Prompt-Nubar Calculations for 27 Actinides

Richard Q. Wright (ORNL, retired), Michaele C. Brady-Raap (PNNL), Robert M. Westfall (ORNL)

Alternative Approach for Importance Ranking of Nuclear Data

Congjian Wang, Bassam Khuwaileh (NCSU), Goran Arbanas (ORNL), Hany Abdel-Khalik (NCSU)

Reactor Physics: General—V

Explanation of Changes in CANDU Coolant Void Reactivity with Creep and Burnup

J. V. Donnelly (AMEC NSS)

A Physics Study on Concave Long-life Sodium-cooled Fast Reactor

Donny Hartanto, Yonghee Kim (KAIST)

Annular Type Sodium Cooled TRU Transmutation Reactor Cores Having Thorium Blankets and Central Non-Fuel Region

Wu Seung You, Ser Gi Hong (Kyung Hee Univ)

Doppler Reactivity Coefficients for Gd Bearing UO2 Fueled Rods with Consideration of Thermal Agitation Effect

Takanori Kitada, Kazuhiro Wada, Koudai Takeichi, (Osaka Univ)

A Burnable Absorber-Integrated Control Rod Guide Thimble for PWR

Mohd-Syukri Yahya, HwanYeal Yu, Yonghee Kim (KAIST)

Finding a Near-Critical VHTR Configuration with a Coupled Neutronics/Thermal Hydraulics Method

Alexander J. Huning, Kevin John Connolly, Srinivas Garimella, Farzad Rahnema (Georgia Tech)

ANS Reactor Physics Division (RPD) Session in Memory of Richard (Dick) McKnight

Dr. Richard McKnight’s Technical Contributions to the Reactor Physics Community, Invited

Temitope A. Taiwo, Robert N. Hill, Hussein S. Khalil (ANL)

Review of the IFR Physics Analysis Database

T. Fei, B. Feng, T. K. Kim (ANL)

Consistent Comparison of Sensitivity Coefficients Obtained with PERSENT and ERANOS Codes

Gerardo Aliberti, Micheal A. Smith (ANL)

Improved ZPR Analysis with the Argonne Reactor Physics Codes

Micheal A. Smith, Richard M. Lell (ANL)

Initial Verification and Validation Tests of the MC2-3 ENDF/B-VII.1 Library for Fast Reactor Systems

C. H. Lee (ANL), W. S. Yang (Purdue Univ), T. A. Taiwo (ANL)

Role of Experiment Covariance in Cross Section Adjustments (Based on Seminal Work Performed by R. D. McKnight), Invited

G. Palmiotti, M. Salvatores (INL)

Nuclear Criticality Safety and Space Technology Applications

Accelerator-Based Intense Fusion Neutron Source

Ross Radel, Greg Piefer, Chris Seyfert, Arne Kobernik, Logan Campbell, Casey Lamers, Tye Gribb, Evan Sengbusch (Phoenix Nuclear Labs)

High Reliability, Long Lifetime, Continuous Wave H- Ion Source Design

Preston J. Barrows, Joseph D. Sherman, Arne V. Kobernik, Tye T. Gribb, Christopher M. Seyfert, Logan D. Campbell, Daniel J. Swanson, Eric D. Risley, Jin W. Lee, Kevin D. Meaney, Evan R. Sengbusch, Ross F. Radel (Phoenix National Labs, Univ of Wisconsin-Madison, TechSource)

A Sensitivity and Feasibility Study on a Small Reactor with LEU Fuel for Space Applications

Hyun Chul Lee (KAERI), Stefan Cerba (KAERI, Slovak Univ of Technology), Hong Sik Lim, Jae Man Noh (KAERI)

Benchmark Evaluation of HTR-PROTEUS Absorber Rod Worths (Core 4)

John D. Bess, Leland M. Montierth (INL)

The Impact of Water Saturation in Graphite Reflector Blocks on NRAD Benchmark Simulation

John D. Bess, Andrew T. Smolinski (INL)

Experimental Thermal Hydraulics

Effects of pH and Electrical Conductivity on the Quantity of Fibrous Debris Bypass through a Containment Sump Strainer

Saya Lee, Rodolfo Vaghetto, Suhaeb Abdulsattar, Matthew Kappes, Yassin A. Hassan (TAMU)

Experimental Study of Pressure Drop through a Fibrous Debris Bed Generated on a Perforated Plate with Embedded Mesh Screen

Suhaeb S. Abdulsattar, Saya Lee, Yassin A. Hassan (TAMU)

Investigation of Abnormal Heat Transfer and Flow in a VHTR Reactor Core

Francisco I. Valentin, Jorge Pulido (City College of New York), Ryan Anderson (Montana State Univ), Masahiro Kawaji (City College of New York, CUNY Energy Institute)

Enhancement of Boiling Performance on a Surface Modified by Micro/Millimeter-Posts and Nanoparticles

Hang Jin Jo, Jin Man Kim, Moo Hwan Kim, Hyun Sun Park (POSTECH),  Hwasung Yeom, K. Sridharan, M. L. Corradini (Univ of Wisconsin-Madison)

Development of Refractive-Index-Matching Technique for Transparent 3D Printing Models for Flow Visualization

Min Seop Song, Hae Yoon Choi, Jee Hyun Seong, Eung Soo Kim (Seoul National Univ)

Experimental Observation of Forced Flow Mixing in Tight-Lattice Rod Bundle

Wang Kee In, Chang Hwan Shin, Chi Young Lee (KAERI)

Turbulence Intensity and Pressure Drop Fluctuations Experienced Downstream of a Mixing Grid

N. C. Galegar, E. E. Dominguez-Ontiveros, Y. A. Hassan (TAMU)

Computational Thermal Hydraulics

3D Model of Evaporation/Condensation at Bubble/Liquid Interface using Level-Set Method

Hong Jiao, M. Z. Podowski (RPI)

Computational Fluid Dynamics Analysis of NGNP Reactor Cavity Cooling System with Air

Huhu Wang, Shamsul Sulaiman, Yassin A. Hassan (TAMU)

Implementing Fully Coupled Subchannel Model into the RELAP-7 Code

Hongbin Zhang, Ling Zou, Haihua Zhao, Richard Martineau (INL), Landon Brockmeyer (TAMU)

Numerical Investigation on the Sensitivity of Permanent Magnet Probe Flowmeter to Velocity Profile

Uiju Jeong (Hanyang Univ), Ji-Young Jeong (KAERI), Sung Joong Kim (Hanyang Univ)

Comparison of RELAP5-3D and TRACE Results for a Boiling/Condensing Experimental Facility

Juan J. Carbajo (ORNL)

Preliminary Investigation of Turbulent Flow Behavior of 3-D Twin Jets using CFD Analysis

L. B. Carasik (TAMU), A. E. Ruggles (Univ of Tennessee), Y. A. Hassan (TAMU)

Thermal Hydraulics: General

Feasibility Studies on the Integration Concept of VHTR and Forward Osmosis Desalination Process

Min Young Park, Eung Soo Kim (Seoul National Univ)

Orificing Strategy for Sodium-Cooled Fast Reactors

F. Heidet, T. K. Kim, T. A. Taiwo (ANL)

Sensitivity Analysis of the Pressure Response of a Typical Large, Dry Containment during a Double-Ended Guillotine Break LOCA using RELAP5-3D and MELCOR

Rodolfo Vaghetto, Alessandro Vanni, Andrew Franklin, Yassin A. Hassan (TAMU)

Numerical Simulation of Countercurrent Flow Limitation at Lower End of a Vertical Pipe

Michio Murase, Takayoshi Kusunoki Institute of Nuclear Safety System, Inc.), Takashi Takata, Akira Yamaguchi (Osaka Univ), Akio Tomiyama (Kobe Univ)

Design of TAMU Air-Cooled Reactor Cavity Cooling System Experimental Test Facility

Shamsul A. Sulaiman, Elvis E. Dominguez-Ontiveros, Huhu Wang, Yassin A. Hassan (TAMU)

Temperature in a Fuel Rod with a Coated Clad and Temperature Dependent Thermal Conductivity

Min-Tsung Kao, Rizwan-Uddin (Univ of Illinois at Urbana-Champaign)

Plenary Session

Modeling and Simulation Coordination at DOE Officce of Nuclear Energy

Marius Stan (ANL), invited

Creating an International Fuel R&D Capability

Fiona Rayment, Daniel Mathers (National Nuclear Laboratory

LWR Accident Tolerant Fuels—I

Status Update on U.S. DOE Accident Tolerant Fuel Development

Shannon M. Bragg-Sitton, Jon Carmack (INL), Frank J. Goldner (DOE), Steven L. Hayes (INL)

Development of Advanced Oxidation Resistant Steel for ATF Clad Application

Lance L. Snead, Kurt A. Terrani, Yuki Tamamoto, Bruce A. Pint, Kevin Field (ORNL)

What Should be the Objective of Accident Tolerant Fuel?

Edward J. Lahoda (Westinghouse), Lars Hallstadius (Westinghouse Electric Sweden AB), Frank Boylan, Sumit Ray (Westinghouse)

Oxidation Mitigation of Zircaloy in High Temperature Steam via FeCrAl Coatings

Brent J. Heuser, Weicheng Zhong, Peter A. Mouche, Mohamed S. Elbakhshwan (Univ of Illinois)

Modeling—I: Fuel Behavior and Performance

Fuels Performance Modeling Based on Microstructure Rather Than Burnup

Michael Tonks, Yongfeng Zhang, Xianming Bai, Derek Gaston, Richard Williamson, Steven Hayes (INL)

Thermophysical Properties of Uranium Dioxide by First-Principles

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

Mechanistic Modeling of Metallic Fuel/Cladding Metallurgical Interactions

Aydın Karahan (ANL)

Molecular Dynamics Calculations of Grain Boundary Mobility in UO₂

Yongfeng Zhang, Xianming (David) Bai, Michael R Tonks (INL)

Validation of Application of Dislocation Punching Condition to Estimating the HBS Pore Pressure

Lijun Gao (Tsinghua Univ/Nuclear Power Inst of China), Bingde Chen (Nuclear Power Inst of China), Shengyao Jiang (Tsinghua Univ)

Advanced Pellet Cladding Interaction Modeling Using the US DOE CASL Fuel Performance Code: Peregrine

Robert Montgomery (PNNL), Nathan Capps (Univ of Tennessee), Dion Sunderland, Wenfeng Liu (ANATECH Corp), Jason Hales (INL), Chris Stanek (LANL), Brian D. Wirth (Univ of Tennessee)

Salt and Gas Reactor Fuels and Materials

Results from the DOE Advanced Gas Reactor Fuel Development and Qualification Program

David A. Petti (INL)

Performance Evaluation of the AGR-1 TRISO fuel: Preliminary Post-Irradiation Examination Results Summary

Paul A. Demkowicz (INL), John. D. Hunn (ORNL), David A. Petti (INL), invited

Status on Irradiation Testing of TRISO Fuel in Korea

Bong Goo Kim, Byung Chul Lee, Moon Sung Cho, Yong Wan Kim (KAERI)

Fission Product Distribution in AGR-1 TRISO Fuel Particles with Varying Silver Retention

Tyler J. Gerczak, John D. Hunn, Charles A. Baldwin (ORNL), Robert N. Morris (UT-Battelle, ORNL)

Fast Reactor Fuels and Materials

Preliminary Post Irradiation Examination of AFC-3A and AFC-3B

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

Phase Characterization in Unirradiated and Irradiated Metallic Fuel for Minor Actinides Transmutation in Fast Reactor

Luca Capriotti (EC-JRC-ITU), K. Inagaki (CRIEPI), D. Papaioannou (EC-JRC-ITU), S. Bremier, H. Ohta, T. Ogata (CRIEPI), R. Eloirdi, F. Bocci, D. Bouexiere, V. V. Rondinella (EC-JRC-ITU)

Characterization of High Energy Xe Ion Damage in U-10Mo Metallic Alloy Fuel with Depth Resolved Synchrotron Microbeam Diffraction

D. Yun, K. Mo, R. Xu, W. Mohamed, B. Ye, M. J. Pellin, A. M. Yacout (ANL)

Distribution of Fuel Elements and Fission Product Elements in the Irradiated Metal Fuels

K. Inagaki (CRIEPI), L. Capriotti (EC-JRC-ITU), H. Ohta, T. Ogata (CRIEPI), S. Bremier, P. Pöml, D. Papaioannou, V. V. Rondinella (EC-JRC-ITU)

Microstructural Evolution in a UZr Alloy Irradiated at Low Fluences

Maria A. Okuniewski (INL), Gary Bell, Joel McDuffee, Ron Ellis, Lance Snead, Bob Sitterson, Stewart Voit (ORNL), Lynne Ecker (Brookhaven National Lab), Brandon Miller, Steven Hayes (INL)

Core Structural Components—I

Development of Silicon Carbide Composite Technologies for Nuclear Applications

Y. Katoh, L. L. Snead, K. A. Terrani (ORNL)

Characterization of Alloy 617 Properties to Support VHTR Intermediate Heat Exchanger Design

L. J. Carroll (INL), T. L. Sham (ORNL), J. K. Wright, R. N. Wright (INL), invited

Inelastic Neutron Scattering Analysis of Reactor-Grade Graphite

A. I. Hawari (NCSU), A. I. Kolesnikov (ORNL), Q. Cai, J. C. Holmes (NCSU), P. D. Ferguson (ORNL)

Permeability Measurements for SiC Ceramic Matrix Composites Relevant to LWR

O. Gutierrez, H. E. Khalifa, C. P. Deck, C. A. Back, R. Schleicher (General Atomics)

Special Session in Honor of Donald Olander—I

Effects of Reactor Exposure on Nuclear Fuel Cladding

Arthur T. Motta (Penn State)

Assessments of Pellet-Clad Gap Conductance and Irradiation Damage Recovery Due to In-Pile Annealing of UO₂: Planned IFA-744 Tests in Halden Test Reactor

S. Yagnik (EPRI), W. Wiesenack (OECD Halden Reactor Project), K. Terrani (ORNL), M. Balooch (Univ of California, Berkeley)

EPRI Root Cause Evaluation of the Fukushima Daiichi Event

Rosa Yang (EPRI)

Combustion of Zirconium-Based Alloys

Albert J Machiels (EPRI)

Mass Relocation by Fission-Induced Creep in U-Mo/Al Dispersion Fuel Meat

Yeon Soo Kim (ANL), G. Y. Jeong, D-S Sohn (UNIST)

Special Session in Honor of Donald Olander—II

Progress in Mechanistic Understanding of Nuclear Materials

Steven J. Zinkle (Univ of Tennessee, ORNL)

Multiscale Modeling of Nanoscale Precipitate Stability in Irradiated Structural Materials

Brian D. Wirth, Donghua Xu (Univ of Tennessee)

Performance of U-Mo Fuel at Low Temperatures

M.K. Meyer, J. Gan, D. D. Keiser, D. M. Wachs (INL)

Oxidation of SiC in High-Temperature Water Vapor

Kurt A. Terrani (ORNL)

Poster Session

UN Kernel Development for Fully Ceramic Microencapsulated Fuels for LWRs

Chinthaka M. Silva (ORNL/Univ of Tennessee), Rodney D. Hunt, Kurt A. Terrani, Stewart R. Voit (ORNL), Terrence B. Lindemer (Harbach Eng and Solutions), Theodore M. Besmann, Lance L. Snead (ORNL)

Enhanced Thermal Conductivity of Metallic Network Reinforced Oxide-based Composite Fuel

Ho Jin Ryu, Joon Hui Kim, Soon Hyung Hong (KAIST)

Thermodynamic Stability of ZrN as Diffusion Barriers for UMo/Al Fuel

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

Oxidation Resistance of Uranium-Silicide Bearing Composites for Advanced Nuclear Reactor Applications

J. T. White, A. T. Nelson, J. T. Dunwoody, K. J. McClellan (LANL)

Synchrotron Radiation Study on Steam Oxidation Behavior of Zircaloy-2 with Advanced Coatings

Kun Mo, Di Yun, Walid Mohamed, Michael Pellin, Jonathan Almer, Abdellatif M. Yacout (ANL)

Oxide Electronic Conductivity and Hydrogen Pickup Fraction in Zr alloys

Adrien Couet, Arthur T. Motta (Penn State), Robert J. Comstock (Westinghouse), Antoine Ambard (EdF)

Superior Thermal Performance of SiC Cladding under Extreme Pool Boiling Conditions

Gwang Hyeok Seo, Gyoodong Jeun, Sung Joong Kim (Hanyang Univ)

Response of Oxide Particles to Externally Applied Stress in Austenitic ODS Alloys

Yinbin Miao (Univ of Illinois), Kun Mo (ANL), Xiang Liu (Univ of Illinois), Zhangjian Zhou (Univ of Science and Technology Beijing), Jonathan Almer (ANL), James F. Stubbins (Univ of Illinois)

Comparison of Nitronic-50 and Stainless Steel 316 for use in Supercritical Water Reactor Environments

Zachary Karmiol, Dev Chidambaram (Univ of Nevada, Reno)

Biaxial Thermal Creep-Fatigue of Inconel 617 at 950ºC

Kuan-Che Lan (Univ of Illinois), Kun Mo (ANL), James F. Stubbins (Univ of Illinois)

Reducing Agent Effects on Haynes-230 in Molten Halide Salts

Luke Olson, Roderick Fuentes, Michael Martinez-Rodriguez, Brenda Garcia-Diaz, Joshua Gray (SRNL)

Pressureless Joining of SiC by Transient Eutectic-Phase Method

T. Koyanagi, J. Kiggans, C. Shih, Y. Katoh (ORNL)

Qualification of Austenitic Steel 316L(N) and Welds for Use as Structural Material in Sodium-Cooled Fast Reactors

Celine Cabet, Laurent Forest, Maxime Sauzay, Yiting Cui, Jean-Louis Courouau (CEA)

Characterization of Non-irradiated Ti-Si-C and Ti-Al-C MAX Phase Materials

Chunghao Shih, Wallace Porter, Roberta Meisner, Yutai Katoh (ORNL), Steven Zinkle (Univ of Tennessee)

Impedance Response of Pre-Oxidized Ferrtic-Martensitic Steels in High Temperature Liquid Sodium Environment: UCFR Application

Sang Hun Shin, Jeong Hyun Lee, Ji Hyun Kim (UNIST)

Molecular Dynamics Study of Thermal Conductivity in Defective Uranium Dioxide

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

Modeling Irradiation Growth of Zirconium and Its Alloy in Nuclear Reactors

Sang Il Choi, Tae Ho Kim, Sang Hun Shin (UNIST), Gyeong-Geun Lee, Junhyun Kwon (KAERI), Ji Hyun Kim (UNIST)

Characterization of High Energy Xe Ion Irradiation Effects in Single Crystal Molybdenum with Depth Resolved Synchrotron Microbeam Diffraction

D. Yun, K. Mo, R. Xu, W. Mohamed, B. Ye, M. J. Pellin, A. M. Yacout (ANL)

Irradiated Microsphere Gamma Analyzer for Examination of Particle Fuel

Charles A. Baldwin, Robert N. Morris, John D. Hunn (ORNL), Paul A. Demkowicz (INL)

Effects of Aging and Heavy Ion Irradiation on Microstructural Evolution in CF8 Cast Austenitic Stainless Steel

Wei-Ying Chen (Univ of Illinois/ANL), Meimei Li, Mark A. Kirk, Pete M. Baldo (ANL), Tiangan Lian (EPRI)

Microstructure Evolution in a 9Cr Ferritic-Martensitic Steel under Ion Irradiation

Cem Topbasi, Arthur T. Motta (Penn State), Mark A. Kirk (ANL)

A Curtaining Removal Technique for Focused Ion Beam Milled U-Mo Fuels

Ryan Collette, Jeffrey King (Colorado School of Mines), Dennis Keiser, Jr., Jason Schulthess (INL)

Phase Stability and Mechanical Properties of Nuclear Grade FeCrAl Under LWR-Relevant Neutron Irradiation

K. G. Field, Y. Yamamoto, L. L. Snead (ORNL)

In-situ X-ray Reflectivity Study of Interfacial Structure Between the Pre-Oxidized Ni(110) Surface and Liquid

Jong Jin Kim, Tae Ho Kim, Seung Hyun Kim (UNIST), Hongping Yan (Carnegie Inst of Washington, HP-CAT), Chi Bum Bahn (Pusan National Univ), Changyong Park (Carnegie Inst of Washington, HP-CAT), Ji Hyun Kim (UNIST)

Hydrogen Migration, Precipitation and Re-Orientation in Nuclear Spent Fuel Cladding in Dry Storage

Nicolas Silva, Yong Yang (Univ of Florida)

Kapitza Resistance of the Grain Boundaries in Ceria

Aleksandr Chernatynskiy (Univ of Florida), David Bai, Jian Gan (INL)

Simulation of Swelling and Stress State in Neutron Irradiated U-10Mo Monolithic Plate

Walid Mohamed, Y. S. Kim, G. L. Hofman, A. M. Yacout (ANL)

Simulation of U-Mo Fuel Swelling to High Burnup

Bei Ye, Yeon Soo Kim, Gerard Hofman, Jeff Rest (ANL)

Diffusion of Cs-137 in a Vented Metallic Fuel for SFR

Chihyung Kim, Yonghee Kim (KAIST)

Development of Advanced In-Pin Metallic Fuel Performance Models for SAS4A

Aydın Karahan (ANL)

Development of Enhanced Mechanistic Model for Metallic Fuel Constituent Redistribution

Aydin Karahan (ANL)

Atomistic Modeling of U₃Si₂ Electronic Structure and Properties

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

Modeling Constituent Redistribution in U-Pu-Zr Metallic Fuel Using the Advanced Fuel Performance Code BISON

Jack Galloway, Cetin Unal, Neil Carlson (LANL), Douglas Porter, Steve Hayes (INL)

Obtaining Elastic Constants using Phase Field Crystal Modeling

Aaron Butterfield (INL), Victor Chan, Susanta Ghosh, Katsuyo Thornton (Univ of Michigan), Michael Tonks, Yongfeng Zhang (INL)

Stress Analysis Study of Silicon Carbide Cladding Under Accident Conditions

V. Avincola (MIT/KIT), K. Shirvan, M. Kazimi (MIT)

Measurement of Hydrogen Generation during Steam Oxidation using Quadruple Mass Spectrometry LA-UR 14-20443

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

Effect of Neutron Irradiation on the Nd-Fe-B Rare-Earth Permanent Magnet

Jie Qui, Adib Samin (Ohio State Univ), Jason Hattrick-Simpers (Univ of South Carolina), Yuan F. Zheng, Lei Cao (Ohio State Univ)

Radiation Resistance of XLPE Nano-Dielectrics for Advanced Reactor Applications

Robert C. Duckworth, Georgios Polyzos, Parans Paranthaman, Tolga Aytug, Keith Leonard, Isidor Sauers (ORNL)

Coherent Quasi-Elastic Neutron Scattering Studies of the Collective Diffusion of Glass-Forming Metallic Liquids

Abhishek Jaiswal, Yang Zhang (Univ of Illinois)

Experimental Validation of the Topological Sensitivity Approach to Elastic-Wave Imaging

Roman D. Tokmashev, Bojan B. Guzina (Univ of Minnesota)

Chromium Oxide Films Formed on Stainless Steel 316 in Molten LiCl-Li2O

Augustus Merwin, Dev Chidambaram (University of Nevada, Reno)

Oxidation and Volatilization of SiC Layer in High Temperature Steam

Byung Ha Park, Cheon No (KAIST)

Review of Fluoride Salt-Cooled High Temperature Reactor LiF-BeF2 (Flibe) Coolant Properties

R. R. Romatoski, L. W. Hu (MIT)

LightGauge Sensor Production and Verification on Nuclear Reactor Materials

Scott McBeath, Eric Burgett (Idaho State Univ)

Bulk Single Crystal Growth of Fuel Materials

Malwina Chaczko, Daniel Isaacs, Eric Burgett (Idaho State Univ)

The Constitutive Modeling of Fracture Toughness in Reactor Pressure Vessel Steel

Pritam Chakraborty, S. Bulent Biner (INL)

Advance the Understanding of the Phases’ Distribution of Triso Fuel Coater using Gamma Ray Computed Tomography (CT)

Neven Ali, Thaar Al-Juwaya, Muthanna Al-Dahhan (Missouri Univ Sci Tech)

Dynamical Recovery in UO₂ Following Radiation Impact

V. Ajay Annamareddy, Xiaojun Mei, Jacob Eapen (NCSU)

Positron Characterization of Neutron Irradiated Reactor-Grade Graphite

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

Modeling—II: Radiation Effects

Radiation Response in FeCr Alloys: The State-of-the-Art

P. Olsson (KTH), L. Malerba (SCK-CEN), invited

Thermochemical Assessment of Advanced LWR Fuel Cladding

T. M. Besmann, Y. Yamamoto, K. A. Unocic (ORNL)

Computer Modeling of Transport of Oxidizing Species in Grain Boundaries during Zirconium Corrosion

Xian-Ming Bai, Yongfeng Zhang, Michael R. Tonks (INL)

Modeling of Neutron Irradiation Hardening of Iron

X. Hu (Univ of Tennessee/ORNL), D. Xu (Univ of Tennessee), T. S. Byun (ORNL), K. A. Terrani (ORNL), B. D. Wirth (Univ of Tennessee/ORNL)

LWR Accident Tolerant Fuels—II

Overview of Properties and Performance of Uranium-Silicide Compounds for Light Water Reactor Applications

A. T. Nelson, J. T. White, D. D. Byler, J. T. Dunwoody, J. A. Valdez, K. J. McClellan (LANL)

Uranium Silicide Fabrication for use in LWR Accident Tolerant Fuel

Jason M. Harp, Paul A. Lessing, Rita E. Hoggan (INL)

MAX Phase Coatings for Accident Tolerant Nuclear Fuel

Brenda Garcia-Diaz (SRNL), Luke Olson (SRNS), Christopher Verst, Robert Sindelar, Elizabeth Hoffman (SRNL), Ben Hauch, Ben Maier, Kumar Sridharan (Univ of Wisconsin-Madison)

Safety of Silicon Carbide Cladding for Fail-Safe Simple Economical SMR (FASES)

Youho Lee, Ho Sik Kim, Hee Cheon No (KAIST)

Development of a High Density Uranium Nitride-Uranium Silicide Composite Accident Tolerant Fuel

Luis H. Ortega, Jordan Evans, Sean M. McDeavitt (TAMU)

Core Structural Components—II

Strengthening of Irradiation-Induced Defects in AISI 304 and 316 Variants

Lizhen Tan, Jeremy T. Busby (ORNL)

Irradiation Effects on LWR Accident Tolerant Fuels Cladding Materials

Tarik A. Saleh, Osman Anderoglu, Stuart A. Maloy (LANL), G. Robert Odette (Univ of California, Santa Barbara), Tobias J. Romero (LANL)

TEM, APT and Hardness Studies of Neutron-Irradiated Ferritic Fe-Cr Single Crystals

Wei-Ying Chen, Yinbin Miao, Carolyn A. Tomchik, Kun Mo (Univ of Illinois), Jian Gan, Maria A. Okuniewski (INL), Y. Q. Wu (Boise State Univ, Center of Advanced Energy Studies), Stuart A. Maloy (LANL), James F. Stubbins (Univ of Illinois)

Nanoparticles Loading Behavior Before and After Matrix Necking: An In-Situ Synchrotron Radiation Study in a 9Cr ODS Alloy

Kun Mo (Univ of Illinois, ANL), Yinbin Miao (Univ of Illinois), Zhangjian Zhou (Univ of Science and Technology Beijing), Di Yun (ANL), Xiang Liu (Univ of Illinois), Jonathan Almer (ANL), James F. Stubbins (Univ of Illinois)

A Study on Compatibility of Ferritic-Martensitic Steels with High-Temperature Sodium for SFR Application

Sang Hun Shin (UNIST), Jun Hwan Kim (KAERI), Ji Hyun Kim (UNIST)

LWR Sustainability and Used Fuel Disposition

Degradation of Concrete for Nuclear Structures: Identified Mechanisms and Knowledge Gaps

Yann Le Pape, Kevin G. Field, Jeremy Busby (ORNL)

Analytical Model Methodology Development and Demonstration of Approach on Used Fuel Performance Characterization for Condition of Normal Transportation

Kenneth Geelhood, Harold Adkins (PNNL)

Alloying and Grain Boundary Structure Effects on the Radiation Induced Segregation Response in Type 304 Variants Under Neutron Irradiation

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

The Effect of Stress Biaxiality on Hydride Reorientation Threshold Stress

M. Nedim Cinbiz, Arthur T. Motta, Donald A. Koss (Penn State)