Winter Meeting 2016 / Volume 115

Full Issue 1

Full Issue 2

Open Plenary: Building Sustainability in the Nuclear Enterprise

ANS President's Special Session

Fukushima Special Session: Enhancement of Risk-Informed Decision Making against External Natural Events- Toward Practical Implementation

General Chair's Special Session: Identifying the Nuclear Grand Challenges

Accelerator Applications: General

Fusion-Driven Subcritical System FDS-SFB and Its Blankes Materials Activation Analysis

Minghuang Wang, Chao Lian, Dehong Chen (CAS)

Multi-Physics Coupling to Model a RbCl-RbCl-Ga Target Stack

E. M. O'Brien, J. M. Doster (NCSU), J. W. Engle, F. M. Nortier, E. R. Olivas (LANL), J. Peeples, M. Stokely (BTI Targetry LLC), I. A. Bolotnov (NCSU)

Biology and Medicine: General

Improving Contrast and Resolution in Plant Root Imaging

Isaac A. Zachary, Scott Kovaleski, Peter Norgard (Univ of Missouri, Columbia)

Evidence of Radiosensitizing Effects of GdPO₄ Nanostructures

Miguel Toro, Jessika Rojas (Virginia Commonwealth Univ)

Evaluation of TiO₂ and TiO₂/Au Nanoparticles as Potential Radiosensitizers by Decomposition of Methylene Blue

M. C. Molina Higgins, J. V. Rojas (Virginia Commonwealth Univ)

Water Scintillation under Proton Beam Exposure

William Christopher Chuirazzi, Ryan Gallagher, Douglas Hardtmayer (Ohio State), Hao Chen, Niek Schreuder (Pronova Solutions), Lei Cao (Ohio State)

Tracking Synthetic Particle Paths Generated in Gate with MPEPT

Roque Santos, Matthew Herald, Arthur Ruggles (Univ of Tennessee, Knoxville)

Updates from Ongoing Nuclear Decommissioning Projects in U.S. and Canada: An Executive Leadership-Panel

Decommissioning and Environmental Sciences: General

Magnetite Dissolution using Hydrazine-Acid Solution for Chemical Decontamination

Seon-Byeong Kim, Hui-Jun Won, Jei-Kwon Moon, Wang-Kyu Choi (KAERI)

Assessment of Reactor BN-350 Influence on Environment during its Operation Period

V. Gluchshenko, P. Chakrov, (Inst of Nuclear), S. DeMuth (LANL)

The Economic and Societal Impact of Baseload Power Generation on Local Communities

Travis S. Carless, Paul S. Fischbeck (Carnegie Mellon Univ)

Study of Reactor BN-350 Wastewater Impact on the Environment

V. Gluchshenko, A. Poleshko (Inst of Nuclear), S. DeMuth (LANL)

Atmospheric ⁴¹Ar Plume Tracking of the UF Training Reactor using a Large-Volume NaI Detector

Hannah E. Gardiner, Jesse Bruner, Kelly A. Jordan, James E. Baciak (Univ of Florida)

Characterization of Plutonium-Contaminated Gloveboxes using a High-Range Alpha Ion Chamber

William Zywiec, Albert Joseph Diaz (LLNL)

NRC Decommissioning Rulemaking: an Update on the Progress and Issues coming out of the Rulemaking Process-Panel

Student Design Competition

Helium-3 Production via Lithium-6 Activation in an Accelerator-Driven Reactor

C. Choi, P. Dressman, A. Jassem, T. Kyle, R. Nicholson, S. Sanders, D. Toneff (Purdue Univ)

Near-Term Deployment Viability of Liquid-Fuel Molten Salt Reactors

S. Bogetic, A. Greenop, N. Haneklaus, C. Poresky, D. Shen (Univ. California, Berkeley)

Design Report of the Molten-Chloride High Temperature Reactor (M-CHTR)

Alex Gross, Andrew Maile, Jordan Rein, John Murphy (Univ. Wisconsin, Madison)

VASIMR^® Interfaced High Temperature Gas-Cooled Fast Reactor for Space Applications

Joe Kelsey, Andrés Morell-Pacheco, Tyler Hughes, Nicholas Whitman, Pavel Tsvetkov (Texas A&M)

Building a Nuclear Energy and Science Education Program: Successes and Challenges of Developing a Vision for Nuclear Energy Education-Panel

Education, Training and Workforce Development

University of Nevada, Reno Graduate Certificate in Nuclear Packaging

Miles Greiner (Univ of Nevada, Reno), Yung Y. Liu (ANL), James Shuler (DOE)

The Use of Ljubljana TRIGA Reactor in Training of NPP Operators and Public Information

Igor Jencic (Jozef Stefan Inst)

Focus on Communications: Talking About Nuclear Waste-What Works and What Doesn't-I -Panel

Focus on Communications: A Picture Really is Worth a Thousand Words-and People Pay attention to them-II -Panel

Research by U.S. DOE NEUP-Sponsored Students-I

Establishing a Database of High Temperature Salt Properties for Nuclear Applications

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

Preliminary Insights on Potential Transitions to Closed Thorium-Based Fuel Cycles

Timothy Ault, Steven Krahn (Vanderbilt Univ)

Computational Studies of Thermal Conductivity of Multiphase Ceramics for Inert Matrix Fuel

Austin W. Travis (Univ of California, Irvine), Andrew T. Nelson (LANL), Martha L. Mecartney (Univ of California, Irvine)

Computational Modeling, Simulation and Analysis of the RPI Walthousen Reactor Critical Facility (RCF)

Matthew D. Eklund, Mathieu Dupont, Peter F. Caracappa, Wei Ji (RPI)

Sensitivity Analysis of an Experimental Breeder Reactor II Fuel Assembly

Emerald D. Ryan, Chad L. Pope (INL)

Development of Zirconium-Silicide Coatings for Improved Performance Zirconium-Alloy Fuel Cladding

Hwasung Yeom, Benjamin Maier, Steven Fronek, Greg Johnson, Elliot Strand Michael Corradini, Kumar Sridharan (Univ of Wisconsin, Madison), Robert Mariani, Xianming Bai (INL), Peng Xu, Ed Lahoda (Westinghouse)

A Scintillation-Fiber Based Cosmic-Ray Muon Tomography System for Imaging Dry Storage Cask

Can Liao, Haori Yang (Oregon State Univ), Zhengshi Liu, Jason Hayward (Univ of Tennessee, Knoxville)

Computed Tomography of Dry Cask Storage for Used Fuel

Christopher R. Greulich, Yuan Gao, Andreas Enqvist, James Tulenko, James E. Baciak  (Univ of Florida)

Research by U.S. DOE NEUP-Sponsored Students-II

Radiation Damage in Multiphase Ceramics

Kenta Ohtaki (Univ of California, Irvine), Maulik Patel (Univ of Tennessee, Knoxville), Martha Mecartney (Univ of California, Irvine)

Structural Properties of Ditechnetium Heptoxide, Tc₂O₇

Daniel S. Mast, Bradley C. Childs, Keith Lawler, Kenneth R. Czerwinski, Alfred P. Sattelberger, Frederic Poineau, Paul M. Forster (UNLV)

Thermal Desorption of Tritium from Fluoride Salt-Cooled Reactor Materials

Alicia M. Elliott, David M. Carpenter, Lin-Wen Hu (MIT)

Development of Critical Experiments to Benchmark Moderator Temperature Reactivity Worth

Mathieu Dupont, Matthew D. Eklund, Wei Ji, Peter F. Caracappa (RPI)

Fabrication of New NFA-SiC Composites for Nuclear Applications

Kaijie Ning, Zhihao Hu, Kathy Lu (Virginia Polytechnic Inst and State Univ)

Radiation Heat Transfer in Molten FliNak

Ethan Chaleff, Tom Blue (Ohio State)

Design of a Symbiotic Device to Harvest Uranium from Seawater through the use of Shell Enclosures

Maha N. Haji, Alexander H. Slocum (MIT)

Cost-Benefit Analysis of High-Strength Materials for Safety-Related Nuclear Reinforced Concrete Shear Walls

Steven M. Barbachyn, Robert D. Devine, Ashley P. Thrall, Yahya C. Kurama (Univ of Notre Dame)

Cutting Edge Technology in Education, Training and Distance Education

E-Learning in Neutron Activation Analysis

Sheldon Landsberger (Univ of Texas, Austin), Peter Bode (NUQAM Consulting), Alesia Lunikova, Danas Ridikas (IAEA), Borut Smodis (Josef Stefan Inst), Marta Almedia (Univ de Lisboa), John Preston (Univ of West Indies)

A Simplified Fission Product Poison Model for Operator Training

Bruce R. Hugo, James E. Stracener (Energy Northwest)

Remote Gamma Ray Spectrum Acquisition

Roel R. Garcia, Felicia Avila, Xue Yang (Texas A&M, Kingsville)

The Innovations in Fuel Cycle Research Awards Program

Effect of Irradiation Mode on Irradiated Microstructure of HT9

E. Getto, Z. Jiao, A. M. Monterrosa, K. Sun, G. S. Was (Univ of Michigan)

Nuisance Alarm Reductions in Organic Scintillation Detector-Based Radiation Portal Monitors

Marc Gerrit Paff, Marc Ruch, Shaun Clarke, Sara Pozzi (Univ of Michigan)

Evaluation of Bentonite Engineered Barrier Performance under Repository Conditions

Rachel N. Pope, Brian A. Powell, Mark A. Schlautman (Clemson Univ)

Equation of State for Technetium Metal up to 153 GPa

Daniel S. Mast, Keith Lawler, Emily Siska, Frederic Poineau, Kenneth R. Czerwinski, Barbara Lavina, Paul M. Forster (UNLV)

Synthesis and Adsorption Studies of a Novel Bifunctional Uranium Chelator

Marek Piechowicz, Wenbin Lin (Univ of Chicago)

Yucca Mountain-Is There a Pulse-Panel

Used Fuel: Once Through or Recycle-Who is Right?-Panel

International Activities on Used Nuclear Fuel Reprocessing Regulatory Framework-Panel

Used Nuclear Fuel Dry Storage Canister Inspection-I

Dry Canister Storage System Inspection and Robotic Delivery System Development

Jeremy Renshaw, Shannon Chu (EPRI)

Development of Robotic Multisensor Inspection System for Used Nuclear Fuel Canisters

C. J. Lissenden, A. M. Motta, Sean Brennan, Karl Reichard (Penn State), I. Jovanovic (Univ of Michigan), T. Knight (Univ of South Carolina), J. Popovics (Univ of Illinois)

Quantitative Determination of Chlorine Concentration by Measurement of Sodium Deposited on Steel via Laser-Induced Breakdown Spectroscopy

X. Xiao, K. C. Hartig, S. Le Berre, A. T. Motta (Penn State), I. Jovanovic (Univ of Michigan)

Nondestructive Evaluation in Steel Structures using Ultrasonic Guided Waves

Lingyu Yu (Univ of South Carolina)

Used Nuclear Fuel Dry Storage Canister Inspection-II

Regulatory Basis for Dry Spent Nuclear Fuel Storage Canister Inspections

Rodney McCullum (Nuclear Energy Inst), Brian Gutherman (Gutherman Technical Services)

Estimating the Penetration Depth and Orientation of Stress Corrosion Cracks using Time-Reversal Acoustics

Marcel C. Remillieux, Pierre-Yves Le Bas (LANL), Lukasz Pieczonka (AGH Univ of Science and Technology), Brian E. Anderson (Brigham Young Univ), T. J. Ulrich (LANL)

Remote Monitoring for Stress Corrosion Cracking in Dry Cask Storage Systems

Paul Ziehl (Univ of South Carolina), Bruce Greer, Jeremy Renshaw (EPRI)

Inspection of Dry Storage Casks using PGAA and NAA Techniques

Jason Brookman, Zeev Shayer (CSM)

Chemistry R&D in Radioactive Waste Management

A New Group Crystallization Approach in Used Nuclear Fuel Recycling-A Look at Fission Product Behavior

James C. Bunsen, Jonathan D. Burns (Texas A&M)

Impacts of Tritium Management Approaches on Tritium Distribution and Capture Requirements for UNF Reprocessing

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

Product Consistency Testing of a Hot Isostatically Pressed Iodine-Containing Waste Form

Stephanie H. Bruffey, Robert T. Jubin (ORNL)

PFLOTRAN Integrated Performance Assessment at Waste Isolation Pilot Plant

HeeHo Park, Glenn Hammond (SNL)

Progress in DOE's Fuel Cycle Technologies Program-Panel

Advanced Aqueous Fuel Cycle-International Perspectives-Panel

Transition to a New Fuel Cycle-Needs and Challenges

Assessing Government and Industry Roles to Accelerate Commercialization of Advanced Reactors and Supporting Fuel Cycles

Steven Krahn, Bethany Burkhardt (Vanderbilt Univ), Andrew Sowder (EPRI)

Going from Closed to Open and Then Back Again: How to Keep a Level Head

Tim Tinsley, Fiona Rayment (NNL)

Transition to a Thorium-Based Fuel Cycle-Choices, Challenges, and Options

Andrew Worrall, Eva Sunny (ORNL), Michael Todosow (BNL), Nick Brown, Florent Heidet (ANL)

Reactor Physics Analysis of Transitioning to a Thorium Fuel Cycle with Molten Salt Reactors

B. R. Betzler, J. J. Powers, A. Worrall (ORNL)

Transition to a U/Pu Fuel Cycle with Fast and Thermal Reactors

Bo Feng (ANL), Eva Sunny (ORNL), Ross Hays (INL), Baptiste Mouginot (Univ of Wisconsin, Madison), Jennifer Littell (Univ of Tennessee, Knoxville), Andrew Worrall (ORNL), Edward Hoffman (ANL)

Transition to Uranium-Based Fast Reactor Fuel Cycle Options

E. Hoffman (ANL), B. Carlsen (INL), Bo Feng (ANL) , Ross Hays (INL), E. Sunny, Andrew Worrall (ORNL)

Impact of Using Cross Sections Versus Recipes in Transition Fuel Cycle Analysis using ORION

Joshua Peterson, Eva Sunny (ORNL), Robert Gregg (NNL)

Fuel Cycle and Waste Management: General-I

A Higher Fidelity Cost Analysis of Wind and Uranium from Seawater Acquisition SymBiotic Infrastructure

Margaret Byers (Univ of Texas, Austin), Maha N. Haji (MIT), Erich Schneider (Univ of Texas, Austin), Alexander H. Slocum (MIT)

The Nuclear Role in Electricity Supply: Moving Away from Baseload

Daniel Curtis, Charles Forsberg (MIT)

Consolidating Data on Spent Nuclear Fuel into a Unified Database

Kaushik Banerjee, Henrik Liljenfeldt, Paul Miller, Joshua L. Peterson, Robert A. Joseph III, Justin B. Clarity, Georgeta Radulescu, Robert A. Lefebvre, John M. Scaglione (ORNL)

Real-Time Solution Analysis in Microfluidic Channels using Raman Spectroscopy

Amanda Casella, Amanda Lines (PNNL), Gilbert Nelson (College of Idaho), Job Bello (Spectra Solutions), Sam Byan (PNNL)

Simulation of Proposed Heat Treatment Methods for the Sister Rods

Nicolas Silva (Univ of Florida), Rose Montgomery (ORNL), Henrik Liljenfeldt, John Scaglione, Bruce Bevard (ORNL)

Impact of Isotope Fidelity on Fuel Cycle Calculations

Baptiste Mouginot, Paul P. H. Wilson, Robert W. Carlsen (Univ of Wisconsin, Madison)

Spent Nuclear Fuel Package Consolidation using Metallic Void Fillers

Yongsoo Park, Thomas J.McKrell, Michael J. Driscoll (MIT)

Fuel Cycle and Waste Management: General-II

CyBORG: An ORIGEN-Based Reactor Analysis Capability for Cyclus

Steve E. Skutnik, Nicholas C. Sly, Jennifer L. Littell (Univ of Tennessee Knoxville)

A Degradation Model and Testing Protocol for Metallic Waste Forms

W. L. Ebert (ANL)

Accelerated Corrosion Tests to Evaluate Long-Term Performance of BORAL® in Spent Fuel Pools

Hatice Akkurt (EPRI), Ashleigh Quigley, Matt Harris (Curtiss-Wright Corp.)

Multicomponent Adsorption of Radioactive Iodine and Krypton using ETS-10 Supported Carbon Nano-Polyhedrons

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

Recent Development in Material Accountancy Techniques for Pyroprocessing Facilities

Safeguards Approach for Pyroprocessing Facilities

Benjamin B. Cipiti (SNL)

Development of a Smart Signal Detection Method for Cyclic Voltammetry via Artificial Neural Intelligence

Samaneh Rakhshan Pouri, Dumidu Shanika Wijayasekara, Milos Manic, Supathorn Phongikaroon  (Virginia Commonwealth Univ)

Multi-Species Modeling of Molten-Salt Electrochemical Process

Sungyeol Choi, Dokyu Kang (UNIST)

Electrochemical Property Determination of Fission Product Elements in Molten Fluoride Salt

Ryan Chesser, Evan Wu, Jinsuo Zhang (Ohio State)

Fusion Energy Technologies

Analysis of Actively Cooled Window for High Power Helicon Plasma Source

Arnold Lumsdaine, Juergen Rapp, Steven Meitner, Rick Goulding, John Caughman (ORNL)

Human Factors, Instrumentation, and Control: Instrumentation

Dead-time Calculations of N-Probe Neutron Detector using Attenuation Law

T. Akyurek (Marmara Univ), S. Usman (Missouri Univ Sci Tech)

Dead-time Determination of Helium Detector using MCNP Code

T. Akyurek (Marmara Univ), L. P. Tucker, S. Usman (Missouri Univ Sci Technol)

Detection of Special Nuclear Material in Cargo using Continuous Neutron Interrogation and Tension Metastable Fluid Detectors

Alex Hagen (Purdue Univ), Brian Archambault (Sagamore Adams Lab, LLC), Rusi Taleyarkhan (Purdue Univ)

High Accuracy Signal Validation Framework for Sensor Calibration Assessment in NPPs

Anjali Muraleedharan Nair, Samuel Boring, Jamie Coble (Univ of Tennessee, Knoxville)

Progress Towards Development of High Temperature Ultrasonic Single Element Transducer

Prathamesh N. Bilgunde, Leonard J. Bond (Iowa State Univ)

Human Factors, Instrumentation, and Controls: Human Factors, Safety, and Safety Systems

Qualitative Evaluation of Human Reliability Analysis Quality

Seungwoo Lee, Dongju Jang, Namchul Cho, Dohyung Kim (KINS)

Modeling the Resilience of Nuclear Power Plant for Unexpected Reactor Trip

Jonghyun Kim, Jooyoung Park (Chosun Univ), Taewan Kim (Incheon National Univ)

Development of Real-Time Quantitative Safety Evaluation Method for Nuclear Power Plants

Seung Geun Kim, Poong Hyun Seong (KAIST)

Quantitative Analysis Guidance in Safety Software Validation

Kenneth Armstrong, Kwok Ivan Chow, Damien Gailliard, Manda Safabash (AREVA)

Gravity Based Non-Invasive Reactor Coolant Inventory Monitoring System

J. Danielson (Oregon State Univ), J. Ridgway (ISL), Q. Wu (Oregon State Univ)

Human Factors, Instrumentation, and Controls: Instrumentation and Control Systems

A Study on Safety Evaluation of Safety Grade Smart Transmitter in Nuclear Power Plants

Hyungtae Kim, Jaeyul Choo, Yeong Jin Yu, Hyun Shin Park (KINS)

Common Cause Failure Mitigation Experience on Digital I&C System in NPP

Man Woo Kim, Jong Jae Choi (KECO Engineering & Construction)

Suggestion of a Framework to Evaluate the Extent of Cyber Security Enhancements in NPP

Chanyoung Lee, Poong Hyun Seong (KAIST)

Establishing a Cyber Security Culture for the Nuclear Industry

Raghu Avali (Westinghouse)

Coupling of Thermal Energy Storage with Small Modular Reactors

J. Michael Doster, Konor L. Frick (NCSU)

Detailed Study of the Transient Rod Pneumatic System on the Annular Core Research Reactor

Brandon Fehr (Georgia Tech)

Advances in Technical Nuclear Forensics: Methods and Analysis-I

National Technical Nuclear Forensics: History and U.S. Research Priorities

Jeffrey Morrison (DHS)

National Technical Nuclear Forensics: U.S. Approach to Capability Sustainment

Amalie Zeitoun (DHS)

Synthesis and Analysis of Glass Analogs for Solid Fallout Debris

Rebecca Carter, Corinne Dorais, Amy E. Hixon (Univ of Notre Dame), invited

Surrogate Post-Detonation Urban Debris (SPUD): Standard Reference Materials 4600 & 4601

Jacqueline L. Mann, Mark A. Tyra, John L. Molloy, Rick Paul, Kenneth G. W. Inn (NIST), JoAnn Buscaglia, Jeffrey Leggitt (Federal Bureau of Investigation), Kevin Pfeuffer, Barbara Fallon, Joshua Dettman (Oak Ridge Inst for Science and Education-FBI), Derek Haws, Sarah Castro, Tony D. Kelly, David Turner, John McClory (AFIT), Simon Jerome (National Physical Lab)

Advances in Technical Nuclear Forensics: Methods and Analysis-II

Gas-Phase Detection of a Multi-Complex Lanthanide Sample for Nuclear Forensics, S.

Adam Stratz, Steven J. Jones, Howard L. Hall (Univ of Tennessee, Knoxville)

Volatility Studies of Lanthanide Hexafluoroacetylacetone Chelates

Shayan Shahbazi, John D. Auxier II, Howard L. Hall (Univ of Tennessee, Knoxville)

Prompt Gamma Neutron Activation Analysis of Niobium for Characterization of Light Interstitials

I. J. Love, S. R. Reese, L. Minc, J. D. Tucker (Oregon State Univ)

Underground Gas Sampling for ³⁷Ar in Hard Limestone

S. R. Biegalski, C. M. Johnson, D. A. Haas, M. Blood (Univ of Texas, Austin)

Nuclear Science User Facility: University Capabilities-Panel

Advanced Manufacturing, Joining and Measurement Techniques

Bond Strength of Plasma Sprayed Zr Diffusion Barrier on U-Mo Fuels

Dustin R. Cummins, Kendall J. Hollis, David E. Dombrowski (LANL)

Mechanical Properties and Characterization of Coated SiC Fuel Cladding

Caen K. Ang, James Kiggans (ORNL), Craig Kemery (NEO Knoxville), Scott O'Dell (Plasma Processes), Joseph Burns, Kurt A. Terrani, Yutai Katoh (ORNL)

Sic-Sic Composite Interphase Evaluation via Small Scale Mechanical Testing

J. Kabel, M. Balooch, Y. Yang (Univ of California, Berkeley), T. Koyanagi, K. Terrani (ORNL), P. Hosemann (Univ of California, Berkeley)

Instrumentation Development for Transient Testing in TREAT

Colby Jensen (INL), Heng Ban, Charles Folsom (Utah State Univ), Robert O'Brien, Troy Unruh, Daniel Wachs, Nicolas Woolstenhulme (INL)

Chloride-Induced Stress Corrosion Cracking Characteristics of the Used Nuclear Fuel Canister Material

Yi Xie, Jinsuo Zhang (Ohio State)

Nuclear Fuels and Materials: Modeling

Rethinking of Zircaloy Embrittlement Criteria for Improving Safety Margin of Light Water Reactor

Youho Lee, Bokyung Kim, Hee Cheon No (KAIST)

Statistical Study of Primary Knock-on Atoms under Neutron Irradiation in RMC Code

Hao Li, Bingyan Zhou, Ganglin Yu, Kan Wang (Tsinghua Univ)

Modeling Crud Attachment on Fuel Surfaces-Role of Interaction Forces

Hitesh Bindra (Kansas State Univ), David Harbottle (Univ of Leeds)

Uncertainty and Sensitivity Analysis of Reactivity Insertion Accidents using BISON Fuel Performance Code

C. Folsom (Utah State Univ), C. Jensen, R. Williamson, N. Woolstenhulme (INL), H. Ban (Utah State Univ), D. Wachs (INL)

Nuclear Fuels and Materials: Fast Reactors and Accident Tolerant Fuel

Fundamental Properties for Evaluation of Uranium-Free TRU-Zr Metal Fuel Performance

Yasushi Tsuboi, Kazuo Arie (Toshiba), Cynthia Papesch, Brandon Miller, Robert D. Mariani (INL), Yuji Arita (Univ. of Fukui), Hirokazu Ohta (CRIEPI)

Morphology and Evolution of 14Cr Powder During Mechanical Alloying for Oxide Dispersion Strengthened Ferritic Alloys

Caleb Massey (Virginia Commonwealth Univ), David Hoelzer, Richard Lowden, Kurt Terrani (ORNL), Steven Zinkle (Univ of Tennessee, Knoxville)

Tensile Behavior of Inconel X750 Sheets: Effect of Heat Treatment

C. Marsh (Univ of South Carolina), D. Kaoumi (NCSU)

Potential Impact of Cladding Wettability on LWR Transient Progression

Aaron Wysocki, Nicholas R. Brown, Kurt A. Terrani (ORNL), Daniel M. Wachs (INL)

Thermal Conductivity and Diffusivity for SiC Fibers for use in ATF Cladding Composites

Troy Munro, Changhu Xing, Kurt Harris, Heng Ban (Utah State Univ)

Thermal Diffusivity Measurement of Irradiated SiC-SiC Composite Material

Zilong Hua (Utah State Univ), Peng Yan, Yanhong Liu, Shuyan Kong, Haihong Xia (SPIC Central Research Inst), Heng Ban (Utah State Univ)

Current Issues in Computational Methods-Roundtable

Deterministic Transport Methods

Fourier Analysis of the Multilevel QD Method with Alpha-Approximation for Time-Dependent Radiative Transfer Problems

Dmitriy Y. Anistratov (NCSU)

A Coarse-Mesh Nonlinear Diffusion Acceleration Scheme with Local Refinement for Neutron Transport Calculations

Dean Wang, Sicong Xiao, Ryan Magruder (Univ of Massachusetts Lowell)

Using Directional Diffusion Coefficients for Nonlinear Diffusion Acceleration of the First Order S_N Equations in Near-Void Regions

Sebastian Schunert (INL), Hans Hammer, Jijie Lou (Texas A&M), Yaqi Wang, Javier Ortensi, Frederick Gleicher, Benjamin Baker, Mark DeHart, Richard Martineau (INL)

A Full Multigrid Method for the Self-Adjoint Angular Flux Equation Based on Cellwise Block Jacobi Iteration

Gabriel Kooreman (Georgia Tech), Daniel F. Gill, Jeffery D. Densmore (BAPL)

Second-Order Method of Characteristics Through Local Cell Refinement

Justin M. Pounders (Univ of Massachusetts Lowell)

Localized Radial Basis Functions for Radiation Transport in Slab Geometry

Brody R. Bassett, Brian C. Kiedrowski (Univ of Michigan)

Pn-FEM Method for Solving the First-Order Neutron Transport Equation

Yunzhao Li, Chao Fang, Hongchun Wu, Liangzhi Cao (Xi'an Jiaotong Univ), Guoshu Zhang (Southwestern Institute of Physics)

Improved Variable-Transformation Algorithm for the Hexagonal Variational Nodal Method

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

The Nuclear Energy Advanced Modeling and Simulation Program-Panel

Computational Methods

GPU Acceleration of History-Based Multigroup Monte Carlo

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

GPU Acceleration of Kernel Density Estimators in Monte Carlo Neutron Transport Simulations

Timothy P. Burke, Brian C. Kiedrowski, William R. Martin (Univ of Michigan), Forrest B. Brown (LANL)

Algorithmic Improvements for Portable Event-Based Monte Carlo Transport using the Nvidia Thrust Library

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

Performance Improvements to the Cross Section Calculation in MPACT

Yuxuan Liu (Univ of Michigan), Shane Stimpson, Kang-Seog Kim, Benjamin Collins (ORNL), Brendan Kochunas (Univ of Michigan)

Penalty-Free Method for Multi-Constrained Optimization Problems Based on Parallel Simulated Annealing

David J. Kropaczek (NCSU)

Theoretical Modeling of Radiation Damaged Polyethylene

B. Z. Xu (Washington State Univ), N. Bowler (Iowa State Univ), S. P. Beckman (Washington State Univ)

Conditional Tree Reduction in the ADAPT Framework

Zachary K. Jankovsky (Ohio State), Matthew R. Denman (SNL), Tunc Aldemir (Ohio State)

Extension of the ADAPT Framework for Multiple Simulators

Zachary K. Jankovsky (Ohio State), Matthew R. Denman (SNL), Tunc Aldemir (Ohio State)

Monte Carlo Methods

Cylindrical Kernel Density Estimators for Monte Carlo Neutron Transport Reactor Physics Problems

Timothy P. Burke, Brian C. Kiedrowski, William R. Martin (Univ of Michigan)

The Iterated Fission Matrix Method

Manuele Aufiero, Yishu Qiu, Massimiliano Fratoni (Univ of California, Berkeley)

Fission Matrix Convergence Diagnostic of the Iterated Fission Probability Method

Aaron G. Tumulak, Brian C. Kiedrowski (Univ of Michigan)

Generalized Sensitivity Calculation in the Monte Carlo Wielandt Method

Sung Hoon Choi, Hyungjin Shim (Seoul Natl Univ)

In-Line Method for Calculating Peak Neutron Absorption by Fission Products Following a Change in Reactor Power

D. P. Griesheimer (Bechtel Marine Propulsion Corp)

Monte Carlo Direct Simulation Method for Initiation Probability Problems

Qi Xu, Gang Xiao, Xuerong Wang (IAPCM)

Mathematical Modeling

On Some Criticality Benchmarks in Spherical Geometry

R. D. M. Garcia (Inst de Estudos Avancados)

Multigroup Transport Equations Derived via Homogeneity and Isotropy Restoration Theory

Nam Zin Cho, YuGwon Jo, Seungsu Yuk (KAIST)

Analytic Solution for Time-Dependent Neutron Transport with Delayed Neutrons via Singular Eigenfunction Expansion

Jeffery D. Densmore (BAPL)

Neutronic-Thermal Hydraulic Benchmark using the SKINATH Point Kinetics Model

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

Derivation of the Point-Kinetics Parameters for the Coupled Reactors

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

Uncertainty Quantification and Sensitivity Analysis

Quantifying the Uncertainty in Deterministic Phonon Transport Calculations of Thermal Conductivity using Polynomial Chaos Expansions

Jackson R. Harter (Oregon State Univ), P. Alex Greaney (Univ of California, Riverside), Todd S. Palmer (Oregon State Univ)

Comparisons Between a Priori Uncertainty Quantification and Calculation/Measurement Discrepancies Applied to the MERCI UO₂ Fuel Rod Decay Heat Experiment

S. Lahaye, T.-D. Huynh, A. Tsilanizara, J. C. Jaboulay, S. Bourganel (CEA)

Time-Dependent Sensitivity Analysis of OECD Benchmark using BISON and RAVEN

Paul W. Talbot (Univ of New Mexico), Kyle. Gamble, C. Rabiti, C. Wang, A. Alfonsi, J. J. Cogliati, D. Mandelli (INL), A. K. Prinja (Univ of New Mexico)

Comparison of Surrogate Model to Physical Model for Dynamic Probabilistic Risk Analysis using the RAVEN Code

Brian Cohn (Ohio State), Andrea Alfonsi, Diego Mandelli, Cristian Rabiti (INL)

Data, Analysis and Operations in Nuclear Criticality Safety-I

Lessons Learned from the Rocky Flats Building 771 Near Miss Criticality Accident

Jerry N. McKamy (DOE)

Point Kinetics Modelling of Decay Heat and the Xenon Effect

George E. Adams, Christopher M. Cooling, Matthew D. Eaton (Imperial College London)

Transitions from Stochastic to Point Kinetics Models In Fissile Solutions

C. M. Cooling, G. E. Adams, M. D. Eaton (Imperial College London)

Development of an In-Beam Neutron Flux Monitor for Time of Flight Capture Measurements

E. Blain, Y. Danon, B. McDermott, A. Youmans, J. Brown, N. Thompson, A. Weltz, K. Mohindroo (Rensselaer Polytechnic Institute), G. Leinweber, R. Block, M. Rapp, D. Barry (Bechtel Marine Propulsion Corp)

The Criticality Safety Program of the Swedish Nuclear Fuel and Waste Management Co (SKB)

Fredrik Sten Johansson (SKB)

Evaluation of Neutron Absorber Panels from Zion Spent Fuel Pool

Hatice Akkurt (EPRI), Matt Harris, Ashleigh Quigley (Curtiss-Wright Corp.)

A Practical Assessment of the Effect of Water Interspersed with Plutonium Metal Hemishells -Summary

Ning Zhang, Mark V. Mitchell, David K. Miko (LANL)

Data, Analysis and Operations in Nuclear Criticality Safety-II

Validation of Criticality Analysis Capability of SuperMC with ICSBEP

Chaobin Chen, Qi Yang, Bin Wu, Guangyao Sun, FDS Team (CAS)

New Version of the MCNP Analytic Criticality Benchmark Suite

Forrest B. Brown (LANL)

Verification of MCNP6.1, MCNP6.1.1, and MCNP6.2-Pre for Criticality Safety Applications

Forrest B. Brown, Michael E. Rising (LANL)

Validation of ²³³U-Fueled Systems in KENO V.a in SCALE 6.2

J. A. Hanna, R. A. L. Rosenthal (U.S. Naval Academy), W. J. Marshall, D. E. Mueller (ORNL), E. L. Jones (Univ of Tennessee, Knoxville), S. R. Blair (U. S. Naval Academy), B. T. Rearden (ORNL)

Adjoint-Based Sensitivity and Uncertainty Analysis for Density and Composition: A User's Guide

Jeffrey A. Favorite (LANL), Brian C. Kiedrowski (Univ of Michigan), Christopher M. Perfetti (ORNL)

A Case Study in the Application of TSUNAMI-3D-Part 1, Multigroup

W. J. Marshall (ORNL), E. L. Jones (Univ of Tennessee, Knoxville), B. T. Rearden, M. E. Dunn (ORNL)

A Case Study in the Application of TSUNAMI-3D-Part 2, Continuous Energy

E. L. Jones (Univ of Tennessee, Knoxville), W. J. Marshall, B. T. Rearden, M. E. Dunn (ORNL), G. I. Maldonado (Univ of Tennessee, Knoxville)

Nuclear Data Testing of Pu239 CIELO Evaluation with NDaST

Ian Hill (Nuclear Energy Agency), James Dyrda (OECD/NEA)

Data, Analysis and Operations in Nuclear Criticality Safety-III

Improvements to Thermal Neutron Scattering Law of CH₂

Kemal Ramic, Carl Wendor, Yaron Danon, Li (Emily) Liu (RPI)

Development of a Thermal Neutron Scattering Law for Polyethylene using Molecular Dynamics Simulations

A. I. Hawari, A. Petersen, Y. Zhu (NCSU), D. P. Heinrichs (LLNL), M. L. Zerkle (BAPL)

Generation of Low Fidelity Experimental Covariance Matrices for ICSBEP Cases

Ian Hill (Nuclear Energy Agency)

Characterization of a Polyethylene Moderated Highly Enriched Uranium System

George McKenzie, Joetta Goda, Travis Grove, Rene Sanchez (INL)

Passive Safety Feature of KIPT Neutron Source Facility

Zhaopeng Zhong, Yousry Gohar (ANL)

Quasi-Differential Neutron Induced Neutron Emission Reaction Measurements at WNR

Kumar S. Mohindroo, E. Blain, Y. Danon (RPI), S. Mosby, M. Devlin (LANL)

Recent Nuclear Criticality Safety Program Technical Accomplishments

Titanium and Aluminum Rod-Replacement Experiments in Fully-Reflected 6.90% Enriched UO₂ Fuel Rod Lattices

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

Subcritical Benchmark of the BeRP Ball Reflected by Tungsten

J. Hutchinson, T. Cutler, B. Richard, A. Sood, Mark Smith-Nelson (LANL)

MCNP Progress for the Nuclear Criticality Safety Program

Forrest B. Brown, Michael E. Rising, Jennifer L. Alwin (LANL)

Finalizing the ⁶³Cu and ⁶⁵Cu Resonance Evaluations for the ENDF/B-VIII Release

Vladimir Sobes, Klaus Guber (ORNL), Luiz Leal (IRSN)

Measurements of the Fission Neutron Spectrum using Threshold Activation Detectors Final Design

Theresa Cutler, Jessie Walker, John Bounds, Travis Grove, Cal Moss, William Myers, Rene Sanchez, Morgan White (LANL)

Analysis Capability and Data Needs Identified during the Evaluation of the SILENE CAAS Benchmarks

Thomas M. Miller, Cihangir Celik (ORNL), Soon Sam Kim (LLNL), Yi-Kang Lee (CEA)

Evaluation of Engineering Controls Implemented to Mitigate Godiva Contamination

J. Goda, J. Bounds, D. Hayes (LANL)

ANS-8 Standards-Forum

The Impact of Chemistry in Nuclear Criticality Safety Evaluations-Panel

Development of MELCOR 2.1 Guidance Report for LPF Applications

David L.Y. Louie, Kyle W. Ross, Larry L. Humphries (SNL)

Particle Resuspension Simulation Capability to Substantiate DOE-HDBK-3010 Data

Tyler G. Voskuilen, Flint G. Pierce, Alexander L. Brown, Fred E. Gelbard, David L.Y. Louie (SNL)

Contaminant Entrainment in a Liquid Fuel Fire with Multi-Component Evaporation Droplet Model

Flint G. Pierce, Alex L. Brown, Ethan Zepper, David L.Y. Louie (SNL)

Evaluating a Historical Airborne Release Test with Modern Modeling Methods

Alexander L. Brown (SNL), Flint Pierce, Ethan Zepper, David L. Y. Louie (SNL), Louis Restrepo (Atkins NS)

Lagrangian 3D CFD Simulation of Turbulent Aerosol Experiments

Sal Rodriguez, Cole Mueller, Bobbi Merryman (SNL)

Fragmentation Prediction for a Brittle Ceramic: A Two-Scale Model Approach.

Pierre-Alexandre Juan, John Bignell, Rémi Dingreville (SNL)

Nuclear Safety R&D at the Department of Energy-II

Development of Advanced Numerical Tools for the Nonlinear Seismic Analysis of Nuclear Systems

Floriana Petrone, Jenna Wong (LBNL), David McCallen, Frank McKenna (LBNL/ Univ of California, Berkeley)

Evaluating Age Effects on HEPA Filters

Charles A. Waggoner Julie Stormo, Chris Boone, Jaime Rickert (Mississippi State Univ)

Miniature High Temperature Testing Unit for HEPA Filter Materials R&D

Juan Nagengast (LLNL)

High Temperature Sealants and Gaskets in Nuclear Applications

Elisa N. Carrillo, Chintalapalle V. Ramana (Univ of Texas at El Paso), Erik Brown, Mark Mitchell (LLNL)

Recent Progress on the Stochastic Objective Decision Aide (SODA) Application

Andrew Maas, Mary Toston, Kushal Bhattarai, Chad L. Pope (Idaho State Univ), Jason P. Andrus (INL)

Current Topics in Probabilistic Risk Analysis-I

Pruning of Discrete Dynamic Event Trees using Density Peaks and Dynamic Time Warping

N. S. Martin, M. R. Denman, T. A. Wheeler (SNL)

Preliminary Cyber-Informed Dynamic Branch Conditions for Analysis with the Dynamic Simplified Cyber MELCOR Model

M. R. Denman, P.L. Turner, R. A. Williams, J. N. Cardoni T. A. Wheeler (SNL)

Effect of Aging and Demand for Reliability Analysis of Degrading Components

Muzhi Zhu, Rachit Aggarwal (Ohio State), Shannon M. Bragg-Sitton (INL), Carol S. Smidts (Ohio State)

Finite-Test-Case Development to Demonstrate Logical Integrity of Software in DRPS

Sung Min Shin (KAERI), Hyun Gook Kang (KAIST), Jaehyun Cho, Wondea Jung (KAERI)

Dynamic Importance Measures in the ADAPT Framework

Zachary K. Jankovsky (Ohio State), Matthew R. Denman (SNL), Tunc Aldemir (Ohio State)

Tuning and Verification of an Internal Flooding Model for Dynamic PRA

Zachary Jankovsky (Ohio State), Richard Denning (Richard Denning, Consultant), Tunc Aldemir (Ohio State)

Rich-Text based PSA Model Transformation and Verification in Risk A

Shanqi Chen, Jin Wang, Jiaqun Wang, Fang Wang, Tongqiang Dang, FDS Team (CAS)

Current Topics in Probabilistic Risk Analysis-II

A Statistical Testing Approach for Quantifying Software Reliability: Application to an Example System

Tsong-Lun Chu, Athi Varuttamaseni, Joo-Seok Baek (BNL)

Probabilistic Risk Assessment of Spent Fuel Pool Cooling System Failure Considering Safety and Security Initiating Events

Mohammad A. Hawila, Sunil S. Chirayath (Texas A&M)

 Identification of Significant NPP Cyber-Attack Scenarios based on Risk Information

Jong Woo Park, Seung Jun Lee (Ulsan Natl Inst Sci Tech)

Analysis of Time Dependent Data and PRA

D. Mandelli, D. Maljovec, A. Alfonsi, C. Picoco, C. Smith, C. Rabiti (INL)

A Simplified Multi-Path Event Tree for the Integral, Inherently-Safe Light Water Reactor (I2S-LWR)

Kellen R. McCarroll, John C. Lee (Univ of Michigan)

Development of a Severe Accident Analysis Engine using Approximate Reasoning

Joomyung Lee, Nam Dinh (NCSU), Tran Cao Son (New Mexico State Univ)

Nuclear Installations Safety: General-I

Severe Accident Modeling for Cyber Scenarios

Jeff Cardoni, Matt Denman, Tim Wheeler (SNL)

An Approach for Assessing Consequences of Potential Supply Chain and Insider Contributed Cyber Attacks on Nuclear Power Plants

Tsong-Lun Chu, Athi Varuttamaseni, Joo-Seok Baek, Susan Pepper (BNL)

Development and Application of Virtual Nuclear Power Plant Platform Concerning Environment and Society Digitally

Yican Wu, Pengcheng Long, Liqin Hu, Fang Wang, Jing Song, Tao He, Jin Wang, Tongqiang Dang, Jingting Zou (CAS)

Fukushima Containment Dose Assessment

Jeff Cardoni, Nathan Andrews (SNL)

Preliminary Assessment of the Dose near the Shield Plug at Fukushima Daiichi Unit 2 (1F2)

Nathan Andrews, Jeffrey Cardoni, Randall Gauntt (SNL)

Time Constants for Optical Fiber Temperature Sensing using a Thermal Resistance Approach

Robert Kenneth Palmer, Kelly M. McCary, Thomas E. Blue (Ohio State)

Nuclear Installations Safety: General-II

Development of the SharkFin Distribution for Fuel Lifetime Estimates in Severe Accident Codes

M. R. Denman (SNL)

Study of Melt Formation and Behavior of a Two-Component Debris Bed in LIVE Facility

A. Miassoedov, X. Gaus-Liu, T. Cron (KIT)

Comparison of HFIR Core Hydraulic Models with Operational Data

Juan J. Carbajo, Prashant K. Jain (ORNL)

Thermal Hydraulics Safety Analyses of TRIGA Reactor upon Fuel Reconfiguration

A. Gairola, D. Gould, J. Geuther, J. Roberts, H. Bindra (Kansas State Univ)

Nuclear Installations Safety: General-III

GSI 191 Closure Issue for EDF PWR Fleet: The Fuel Assembly Test Results

Gilles Champion, Thomas Goubin (EdF)

Failure Diagnosis for the Holdup Tank System via ISFA

Huijuan Li (Ohio State), Shannon Bragg-Sitton (INL), Carol  Smidts (Ohio State)

Characteristics Analysis of SGTR Accidents under the Shutdown Conditions

Wook-Jo Lee, Dong-Wook Jerng (Chung-Ang Univ), Seoung Su Jeon, Soon Joon Hong (FNC Technology Co. Ltd.)

Systems Engineering (SE) Approach of Developing a Passive Safety Injection System (PSIS) to Cope with APR 1400 Extended Station Black-Out (SBO) Accident using RELAP5

A. K. Shiran, S. J. Oh (KINGS)

PWR Station Blackout and External Events Analysis for LWRS/RISMC Project

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

Intersection of Policy Development and Technical Innovation for Nuclear Nonproliferation and Security

Development of a Discrete Event Simulation Model for Pyroprocessing Safeguardability

R. A. Borrelli, Malachi Tolman (Univ of Idaho)

The Effect of Localized Pin Flux on Short-Term Gamma Intensities of Spent Fuel Assemblies

B. J. Adigun, H. R. Trellue, G. J. Dean, S. J. Tobin, J. D. Galloway (LANL)

Material Balance Area Design for the Transuranic Fuel Cycle Employing High Temperature Gas Cooled Reactors

Takeshi Aoki (Tokyo Inst Technol), Sunil S. Chirayath (Nuclear Security Science & Policy Inst, Hiroshi Sagara (Tokyo Inst Technol)

Estimation Technique of Cs Retention Fraction in Irradiated Nuclear Fuel with Intact/Damaged Form

Hiroshi Sagara, Kazuki Nakahara, Chi Young Han (Tokyo Inst Technol)

Critical and Subcritical Experiments

The 2016 Edition of the ICSBEP Handbook

John D. Bess, Margaret A. Marshall (INL), Jim Gulliford, Ian Hill (Nuclear Energy Agency)

The PRINCESS Project: An IRSN Project for Experimental Data Acquisition in the Frame of Criticality Safety and Reactor Physics

I. Duhamel, Eric Letang (IRSN)

Comparison of the Performance of Various Correlated Fission Multiplicity Monte Carlo Codes

Jennifer Arthur (Univ of Michigan), Rian Bahran, Jesson Hutchinson, Michael Rising (LANL), Sara Pozzi (Univ of Michigan)

Development of a Research Reactor Protocol for Neutron Multiplication Measurements

R. Bahran, J. Hutchinson, J. Arthur, A. Sood (LANL), P. Caracappa, N. Thompson (RPI), S.  Pozzi (Univ of Michigan)

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

Rene Sanchez, Travis Grove, George McKenzie, Joetta Goda, John Bounds, Theresa Cutler, David Hayes (LANL)

Preliminary Design of the TEX-MOX Criticality Experimental Program using Optimization Algorithms Implemented in the IRSN PROMETHEE Tool

M. Brovchenko, I. Duhamel, R. Salmon, Y. Richet (IRSN)

Use of Criticality Eigenvalue Simulations for Subcritical Benchmark Evaluations

J. Hutchinson, T. Cutler (LANL)

Advanced Gen IV Reactors

Helium Brayton Cycle Design for Advanced High Temperature Reactor System

I. Skavdahl, V. Utgikar, R.N. Christensen (Univ of Idaho), P. Sabharwall (INL), M. Chen, X. Sun (Ohio State)

Density Effects on Lock Exchange Flow During a DCC

Molly Glass, Brian Woods, Seth Cadell (Oregon State Univ)

Overview and Purpose of the 52 Reactors that were Built at INL-Panel

Operations and Power: General-I

An Economic Model of a Steam Accumulator Storage System for Nuclear Power Plants

Alina LaPotin, Erich Schneider (Univ of Texas, Austin)

The Zero-Discharge Policy and its Implications for Tritium Inventory at Columbia Generating Station

Bruce R. Hugo, Glenn M. Pierce (Energy Northwest)

Analysis of ELAP and Mitigation Strategies in Maanshan PWR with PCTRAN

Y. T. Hsu, J. H. Yang (Natl Tsing Hua Univ), S. C. Chiang, T. Y. Yu (Taiwan Power Co.), C. Shih (Natl Tsing Hua Univ)

Potential Ancillary Services Revenue for Nuclear Power Plants with Thermal Energy Storage

W. Neal Mann, Erich A. Schneider (Univ of Texas, Austin)

Systems Safety Evaluation based on System Thinking

Hiroshi Ujita (Inst for Environmental & Safety Studies)

Operations and Power: General-II

Benchmark of Spacer Grid Models Used In Nuclear Power Plants

Alan B. Maskal, Fatih Aydogan (Univ of Idaho)

Packed Bed Thermal Storage for Compact Light Water-Cooled Small Modular Reactors

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

Sensitivity Study of PWR Upper Vessel Flow and Phenomena using RELAP5-3D

Timothy Crook, Rodolfo Vaghetto, Alessandro Vanni, Yassin A. Hassan (Texas A&M)

Modeling PWR Systems with a Unique Framework for Hybrid Energy Systems

Fatih Aydogan (Univ of Idaho)

Challenges (Financial Challenge) with Current Operation Fleet-Panel

Advanced Reactors-Panel

New Nuclear Construction Around the World-Status Report-Panel

Emerging Issues in Supply Chain-Panel

Novel Detection Methods

Thin-Film Solid State Active Dosimetry

Erin Vaughan, Adam Hecht, Ganesh Balakrishnan, Sadhvikas Addamane, Eduardo Padilla (Univ of New Mexico)

Some Non-Equilibrium Effects of Gamma Dose Deposition in Brick

Robert B. Hayes (NCSU)

Evaluation of MSNDs for Fast-Neutron Detection and the TREAT Hodoscope

Priyarshini Ghosh, Wenkai Fu, Ryan Fronk, Douglas S. McGregor, Jeremy A. Roberts (Kansas State Univ)

Computational Tools for Radiation Protection and Shielding

Dose Mapping from a DD Neutron Generator at the University of Sharjah

Walid A. Metwally, Osama A. Taqatqa, Mohammed M. Ballaith (Univ of Sharjah), Allan X. Chen, Melvin A. Piestrup (Adelphi Technology)

Advanced Capability of Monte Carlo Transport and Depletion Calculation Program SuperMC for Fusion and Fission Applications

Jing Song, Lijuan Hao, Chaobin Chen, Yican Wu, FDS Team (CAS)

Shielding Analysis of TN-32 Spent Fuel Dry Cask with SCALE

Yuan Gao, Haitang Wang, James E. Baciak, Andreas Enqvist (Univ of Florida)

Assessment of Multi-Step CADIS Parameter Sensitivity to Neutron Flux Spectrum in Shutdown Dose Rate Calculations

Ahmad Ibrahim (ORNL), Lucas J. Jacobson (Univ of Wisconsin, Madison), Scott W. Mosher, William A. Wieselquist (ORNL)

Predicting Solar Modulation Potentials for Modeling Cosmic Background Radiation

P. A. Behne, G. E. McMath, G. W. McKinney, C. M. Marianno (LANL)

Using Python for 3D Visualizations of MCNP Output

C. W. Arnold (Pajarito Scientific Corp.)

Delayed-Gamma Energy Biasing with Exact Energy Sampling in MCNP 6.2.0

J. R. Tutt, C.A. Anderson, G. W. McKinney (LANL)

Radiation Protection and Shielding: General

Computational Study of 15 MeV Linac Radiation Doses at UNLV Accelerator Facility

Matthew Hodges, Alexander Barzilov, Yitung Chen (UNLV)

Comparison of the MCNP6 and FLUKA Codes in Shielding Calculation at ProNova Proton Therapy Facility

Z. Xia, V.P. Derenchuk (Ponova Solutions LLC), Doug Hardtmayer, Lei Cao (Ohio State), L. Derenchuk, H. Chen, M. Hansen, R. Moore, Z. Nevitt, J. Volk (Pronova Solutions, LLC)

Characterizing Fluence as a Function of Areal Density for 1 and 14 MeV Neutrons Transported Through Air

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

Shielding and Activation Analyses for Beam Test Facility at SNS

Irina I. Popova, Franz X. Gallmeier (ORNL)

Dose Rate Investigation for Cobalt Isotope Rods Retrieval Campaign

C. Fung Poon, K. Bennett (GE-Hitachi Nuclear)

Tritium Release Limit for Fluoride Salt-cooled High-temperature Reactors

Xiao Wu, Sheng Zhang, Shanbin Shi, Xiaodong Sun (Ohio State), David Holcomb (ORNL), Richard N. Christensen (Univ of Idaho), Piyush Sabharwall (INL)

Radiation Protection and Shielding-Roundtable

Reactor Physics: General-I

An Overview on the Role of Nuclear Data: Analysis and Evaluation

Luiz Leal (IRSN)

Resonance Self-Shielding using Deterministic Transport Methods with Pointwise Cross Sections

Mark L. Williams (ORNL)

Characterization of the Pulsed Radiation Environment in FREC-II at the ACRR

Nicholas Whitman, Bradley Cox (LANL)

Phenomena Identification and Ranking Table (PIRT) for Fluoride High-Temperature Reactor (FHR) Neutronics

Farzad Rahnema, Dingkang Zhang, Bojan Petrovic (Georgia Tech), David Diamond (BNL), Dumitru Serghiuta (CNSC), Christopher Edgar (Georgia Tech), Max Fratoni (Univ of California, Davis), Hans Gougar (INL), Ayman Hawari (NCSU), Jianwei Hu (ORNL), Nathanael Hudson (NRC), Dan Ilas (ORNL), Ivan Maldonado (Univ of Tennessee, Knoxville)

Uncertainty Quantification of Spatial Correction Factor for Sjöstrand Method due to Cross-Section Data

Toshiki Kimura, Tomohiro Endo, Akio Yamamoto (Nagoya Univ)

Uncertainty Quantification of Activation Due to Cross Section Data in Neutron Shielding Calculation

Kimihiro Yokoi, Tomohiro Endo, Akio Yamamoto, (Nagoya Univ), Ryoji Mizuno, Yoshio Kimura (Chuden-CTI)

Channel Bow Constraint Option in the BWR Loading Pattern Optimization System FINELOAD-3

Akihiro Fukao, Takashi Yoshii, Yusuke Kuroda (TEPCO Systems Corp)

Reactor Physics: General-II

Quantifying Transient Uncertainty in the BEAVRS Benchmark using Time Series Analysis Methods

Shikhar Kumar, Jingang Liang, Benoit Forget, Kord S. Smith (MIT)

Dynamic Simulation with on the Fly Doppler Broadening Treatment in RMC

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

Benchmark Comparisons of Lattice Physics Calculations for Thorium-Based Fuels in Pressure-Tube Heavy Water Reactors

A.V. Colton, B.P. Bromley, C. Dugal, H. Yan, and S. Golesorkhi (Canadian Nuclear Laboratories)

Status and Ongoing Developments for the GeN-Foam Multi-Physics Solver

Carlo Fiorina (EPFL), Andreas Pautz (EP FL-Paul Scherrer Inst)

MCNP6 Modification for the Calculation of Rossi and Feynman Distributions

A. Talamo, Y. Gohar (ANL)

Investigation of Heterogeneity Effects on Calculated Sensitivities of the ZPPR-15B Assemblies

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

Variational Nodal 2D/1D Transport/Diffusion Solutions of the C5G7 Benchmark Problems

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

Reactor Physics: General-III

Enrichment Penalty for Molybdenum Cladded Accident Tolerant Fuel

Steven A. Thompson (Dominion)

Mesh Adaptive Search Optimization in SERPENT2 Stereolithography Geometry

A. Talamo, Y. Gohar (ANL), J. Leppänen (VTT)

Measurement of Kinetic Parameters by Oscillated Experiments

Sandra Dulla, Hoh Siew Sin, Piero Ravetto (Politecnico di Torino), Paolo Saracco (INFN)

Treatments for Neutron Resonance Elastic Scattering using the Multipole Formalism in Monte Carlo Codes

Vivian Y. Tran (MIT), Jonathan A. Walsh (LLNL), Benoit Forget (MIT)

Reactor Physics: General-IV

Small CaH₂ Moderated Thermal Reactor for Surface Power Generation I: Conceptual Design

Rei Kimura, Taishi Yoshida, Satoshi Wada, Yoshihiro Hyodo, Yoshiro Nishioka, Kunio Hoshino (Toshiba)

Small CaH₂-Moderated Thermal Reactor for Surface Power Generation II: Core Neutronics Design

Satoshi Wada, Rei Kimura, Taishi Yoshida, Yoshiro Nishioka, Yoshihiro Hyodo, Kunio Hoshino (Toshiba)

Optimal Temperature Grid for Accurate Doppler Kernel Reconstruction

Pablo Ducru, Karia Dibert, Colin J. Josey, Benoit Forget (MIT), Vladimir Sobes (ORNL), Kord Smith (MIT)

Benchmark for Free-Gas Elastic Scattering with the Heavy-Gas Model and Piecewise-Constant Cross Sections

Matthew A. Gonzales, Anil K. Prinja (Univ of New Mexico), Brian C. Kiedrowski (Univ of Michigan), Forrest B. Brown (LANL)

Ab Initio Generation of Thermal Neutron Scattering Law for Uranium Dioxide

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

Impact of Spatial Discretization on Reactivity Biases in Depleted TRIGA Fuel

Ye Cheng, Jeremy A. Roberts (Kansas State Univ)

A BWR Fuel Assembly Concept with Partial Segregation of Fertile Material

F. Y. Odeh, W. S. Yang (Purdue Univ)

Reactor Physics: General-V (WP7)

Neutronics Code Benchmark for Fluoride-Salt-Cooled Reactors

Lance Maul (ANSTO/ UNSW), Dan Shen, Massimiliano Fratoni (Univ of California, Berkeley)

Commercial-Scale, Fluoride-Salt-Cooled, High-Temperature Reactors with Novel Refueling and Decay Heat Removal Capabilities

Justin Pounders (Univ of Massachusetts Lowell), Charles Forsberg (MIT), Rich Kochendarfer (AREVA), Eugene Shwageraus, Geoff Parks (Univ of Cambridge)

Preliminary Neutronic Assessment of a Novel Fluoride-Salt-Cooled High-Temperature Reactor Design

Yao Li, Justin M. Pounders (Univ of Massachusetts Lowell)

Depletion Analysis of Additively Manufactured Control Elements in HFIR

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

Criticality Control of a High-Performance Soluble-Boron-Free Small Modular Reactor Core

Mohd-Syukri Yahya, Yonghee Kim (KAIST), Chang Kyu Chung (KEPCO)

The Water Ingress Effects on the Reactivity Change of the Conceptual Designed Reactor at NIST

Zeyun Wu, Robert E. Williams (NIST)

HFIR Core Modeling and Analysis for PROSPECT Reactor Antineutrino Experiment

Andrew Conant (Georgia Tech)

Reactor Physics: General-VI

Reactivity Impact of Accident Tolerant Claddings in an Equilibrium PWR Core

Troy A. Eckleberry, G. Ivan Maldonado (Univ of Tennessee, Knoxville)

Analysis of a Nuclear Data Experiment: MANTRA-3

Jyothierkumar Nimmagadda (Univ of Florida) Giuseppe Palmiotti, Gilles Youinou (INL), George Imel (Univ of Florida)

Preparatory Verification of a New Monte Carlo Code cosRMC based on VERA Core Physics Benchmark

Hui Yu, Yao Qin, Guoping Quan, Xing Wang, Yixue Chen (SNPSDC)

Reactor Analysis Methods-I

Predicting Correlation Coefficients for Monte Carlo Eigenvalue Simulations

Jilang Miao, Benoit Forget, Kord Smith (MIT)

Prediction on Underestimation of Statistical Uncertainty in Monte Carlo Eigenvalue Calculation for Two-Dimensional Heterogeneous Color Set Geometry

Koji Hayashi, Tomohiro Endo, Akio Yamamoto (Nagoya Univ)

Application of Variance Reduction Techniques in RMC Burnup and Thermal-Hydraulic Coupled Calculation

Qu Wu, Shichang Liu, Juanjuan Guo, Kan Wang (Tsinghua Univ)

Spatially Continuous Depletion Algorithm for Monte Carlo Simulations

Matthew S. Ellis, Colin Josey, Benoit Forget, Kord Smith (MIT)

Dynamic Monte Carlo Transient Analysis with Thermal-Hydraulic Feedback by McCARD/CUPID

Soomin Kang, Nadeem Shaukat, Hyungjin Shim, Hyoung-Kyu Cho (Seoul Natl Univ)

Improved Few-Group Homogenized Cross-Section Sensitivity Analysis for Lattice Physics Calculation

Liangzhi Cao, Yong Liu, Hongchun Wu (Xi'an Jiaotong Univ)

The Effects of Different Lattice Codes on Results of Sensitivity and Uncertainty Analysis

Liangzhi Cao, Chenghui Wan, Hongchun Wu (Xi'an Jiaotong Univ)

Unbiased Ratio Estimator for k-Eigenvalue in Monte Carlo Criticality Calculations

YuGwon Jo, Nam Zin Cho (KAIST)

Reactor Analysis Methods-II

Application of Simplified Pn Approximation to Angular Distribution of Neutron Source in MOC Calculations

Akio Yamamoto, Akinori Giho, Tomohiro Endo (Nagoya Univ)

Comparison of the Numerical Stability between CMFD and GCMR with Stabilization Techniques

Akinori Giho (Univ of Pittsburgh), Akio Yamamoto (Nagoya Univ)

Verification of the 2D Finite Element SP₃ Solutions

Eun Hyun Ryu, Yong Mann Song (KAERI)

Implementation of a Red-Black SOR CMFD Solver in MPACT

Shane Stimpson, Benjamin Collins (ORNL)

A Study on Reconstruction of Intra-Pin Information in Pin-Wise Reactor Analysis

Xuan Ha Nguyen, Yonghee Kim (KAIST)

Application of NEM-Based Pin-by-Pin HCMFD Algorithm to 3-D Core Analysis

Jaeha Kim, Yonghee Kim (KAIST)

Reactor Analysis Methods-III

Comparison of Fuel Loading Pattern Optimization Results using Exhaustive Search for Fresh Fuels and Local Search for Burned Fuels

Satomi Ishiguro, Tomohiro Endo, Akio Yamamoto (Nagoya Univ)

A Methodology for Loading the Advanced Test Reactor Driver Core for Experiment Analysis

Wilson M. Cowherd (INL), Joseph W. Nielsen (Battelle Energy Alliance), Dong Choe (INL)

Solution of the C5G7 Benchmark using the MOCUM Transport Code with ANSYS Unstructured Mesh

Makanjuola M. Adara, Xue Yang (Texas A&M, Kingsville)

Neutronics and Computational Fluid Dynamics Analyses for a Natural Circulation Loop of Molten Fuel Salt

R. J. Sheu, C. H. Chuang, Y. M. Ferng (Natl Tsing Hua Univ), O. Feynberg (Kurchatov Inst)

Reactor Analysis Methods-IV

Neutronics/Thermal-Hydraulics Coupling with RMC and CTF for BEAVRS Benchmark Calculation

Juanjuan Guo, Shichang Liu, Xiaotong Shang, Kan Wang (Tsinghua Univ)

Dead-Time Correction of Pulsed Neutron Source Experiments with the Backward Extrapolation Method

A. Talamo, Y. Gohar (ANL)

On-the-Fly Doppler Broadening with Probability Table Interpolation for Unresolved Resonance Region in RMC

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

The Reducibility of Reactor Physics Depletion and Decay Calculation

Siqi Zhang, Hany S. Abdel-Khalik (Purdue Univ)

Fast Reactors

Improved Gamma Yield and Interaction Cross-Section Libraries of MC²-3

B. K. Jeon, W. S. Yang (Purdue Univ), C. H. Lee (ANL)

Coupled Neutron and Gamma Heating Calculation Based on VARIANT Nodal Transport Method

Puran Deng, Won Sik Yang, Gang Yang (Purdue Univ)

MC²-3/DIF3D Analysis of the ZPPR-15B Foil Measurements

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

Impact of Americium-241 (n, γ) Branching Ratio on SFR Core Reactivity and Spent Fuel Characteristics

Hikaru Hiruta, Gilles J. Youinou, Brent W. Dixon (INL)

SE2-ANL Subchannel Analysis with New Heating Calculation Based on VARIANT Transport Code

G. Yang, W. S. Yang, P. Deng (Purdue Univ)

CANDLE Burning Reactor with Plutonium Fuel Start-up Core

Toru Obara, Jun Nishiyama, Hiroki Osato (Tokyo Inst Technol)

Ultra-Long-Life Cores having Axial Blanket-Driver-Blanket Burnup Strategy with Thorium and PWR Spent Fuels

Ser Gi Hong, HaeLee Hyun, Wuseung You (Kyung Hee Univ)

An Investigation on the Sustainability of a Sodium-Cooled Breed-and-Burn Fast Reactor (B&BR)

Chihyung Kim (KAIST), Donny Hartanto (KAERI), Yonghee Kim (KAIST)

Reactor Physics Design, Validation and Operational Experience-I

A Simulation of Rod Ejection Accident in an Advanced Small PWR Core without Soluble Boron

Hoseong Yoo, Ser Gi Hong (Kyung Hee Univ)

Data Assimilation Needs for RR Performance Improvement

Evgeny Ivanov (IRSN), Perry Young (NRG)

Criticality Benchmarking of the Oregon State TRIGA Reactor using the MCNP Burn Option

R. A. Schickler, T. S. Palmer (Oregon State Univ)

The 2016 Edition of the IRPhEP Handbook

John D. Bess, Margaret A. Marshall (INL), Jim Gulliford (OECD/NEA), Ian Hill (Nuclear Energy Agency)

MOCUM Verification with a Heterogeneous MOX Whole Core C5G7 Benchmark Problem

Ayoola Oredeko, Xue Yang (Texas A&M, Kingsvile), Zeyun Wu (NIST)

An Analysis Method for Experiment Power in the ATR

Joseph W. Nielsen (Battelle Energy Alliance), David W. Nigg, Nicolas E. Woolstenhulme, A. Andy Beasley (INL)

Neutronics Analysis of Fuel-in Fiber Concept

Briana Hiscox, Koroush Shirvan (MIT)

Reactor Physics Design, Validation and Operational Experience-II

Uncertainty due to Nuclear Data for an MTR Fuel Assembly

D. F. da Cruz (NRG)

Use of Solid Pyrex Rod for Conceptual Soluble Boron Free SMR

Jinsun Kim, Hyoje Cho, Manseok Do, Kibong Seong (Kepco NF)

Benchmark Study of Infinite Lattice of Pebble Fuel within FLiBe Coolant for TMSR-SF1 Design

Ruimin Ji, Yafen Liu, Yang Zou (SINAP), Kaichao Sun, Lin-wen Hu (MIT)

The Optimized Parallel MOC Module in Code cosLATC

Shuo Li, Chenglin Zhu, Hui Yu, Yuhang Yan, Yixue Chen (SNPSDC)

Comparison of Proposed HANARO Fuel Assemblies in the WWR-SM Reactor

L. M. Peguero, T. S. Palmer (Oregon State Univ)

Application of PCM Validation to BFBT Experiments

Jia Zhou (Purdue Univ), Guojun Hu (Univ of Illinois), Hany Abdel-Khalik (Purdue Univ)

TREAT

Improved Quasi-Static Method with Step Doubling Time Adaptation

Zachary M. Prince, Jean C. Ragusa (Texas A&M)

Local Doppler Broadening Effects from Thermal Neutrons during Transient Testing

Logan M. Scott (Texas A&M), Samuel E. Bays (INL), Jean C. Ragusa (Texas A&M)

A Neutron Streaming Problem to Test Rattlesnake Methods for TREAT

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

Transient Reactor Test Facility (TREAT) Startup Status

J. R. Parry (INL)

A Parametric Study of the Adjoint Flux Calculation for TDKENO

Dustin Popp, Zander Mausolff (Univ of Florida), Mark DeHart (INL), Sedat Goluoglu (Univ of Florida)

Testing of Graphite Thermal Neutron Scattering Law Data in Support of TREAT Neutronic Analysis

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

Parallel Performance of the Time Dependent Transport Code TDKENO with Applications to TREAT Simulations

Zander Mausolff (Univ of Florida), Mark DeHart (INL), Sedat Goluoglu (Univ of Florida)

Conceptual Phase Neutronic and Thermal Analyses for the LEU Conversion of the Transient Reactor Test Facility (TREAT)

Heather M. Connaway, Dimitrios C. Kontogeorgakos, Dionissios Papadias, Arthur E. Wright (ANL)

Robotics and Remote Systems Topics

A Machine Learning Based System Performance Prediction Model for Transportable FHR

Yuyun Zeng, Jingquan Liu (Tsinghua Univ), Kaichao Sun, Chenglong Wang, Lin-wen Hu (MIT)

Development of Plug-and-Play Interchangeable Components for Unmanned Aerial System with Mobile Manipulation Capability

Jameson Lee, Jessica Hartman, Zachary Cook, Joon S. Lee, Woosoon Yim, Alexander Barzilov (UNLV)

Contour Mapping Based Radiation Source Localization by UAS Swarm

Zachary Cook, Jameson Lee, Jessica Hartman, Alexander Barzilov, Woosoon Yim (UNLV)

Role of Disaster Robot from the Perspective of HTO-Based Safety Assurance

Young Choi, Kyung Min Jeong (KAERI), Inn Seock Kim (ISSA Technology, Inc)

Computational Thermal Hydraulics

Toward Linear Stability Analysis of Upper Plenum Flows

John Mulloy (Texas A&M), Elia Merzari, Oana Marin (ANL), Yassin Hassan (Texas A&M)

Computational Fluid Dynamics Simulation of a Pilot-Scale Waste Glass Melter

Alexander Abboud , Donna Post Guillen (INL)

Modeling Analysis for Nuclear Material Transport Package

Si Y. Lee (SRNL)

Development of Multiple Solid Components Capability in GOTHIC Droplet Fields

Nate Carstens, Tom George (Numerical Applications)

Preliminary Development of a Drift-Flux Model Based Pin-Resolved Core Thermal-Hydraulic Code for Dedicated Use in Efficient High-Fidelity Neutronics Coupled Calculations

Jaejin Lee, Han Gyu Joo (Seoul Natl Univ)

Assessment of a Smoothed Particle Hydrodynamics Method for Thin Film on Textured Surface

Linyu Lin, Nam Dinh (NCSU)

Fuel Rod Thermo-Mechanic Analysis of Kuosheng NPP in MSIVC Transient with RELAP5 MOD3.3/FRAPTRAN/Python Code in SNAP Interface

H. C. Chang, C. Shih, J. R. Wang (Natl Tsing Hua Univ), S. C. Chiang, T. Y. Yu (Taiwan Power Co.), I. C. Lee, W. S. Hsu (Natl Tsing Hua Univ)

In Memory of Salomon Levy on His Technical Contributions to the Advancements of Thermal Hydraulics-Panel

Technical Achievement Award Lecture

Toward a Longer-Life Core: Thermal-Hydraulics Simulations and Experiments of Deformed Fuel Assemblies

Experimental Data Sets for CFD Calculations of Flow and Heat Transfer in Deformed Fuel Assemblies

Brian E. Mays (AREVA Inc.), R. Brian Jackson, Tom Reeves (TerraPower LLC), Nate Salpeter (AER Consulting)

Heated Bundle Test in AREVA Inc. Fuel Cooling Test Facility

Mathieu Martin, Kelly Duggan, Tom Galioto (AREVA NP)

Flow Field and Pressure Measurements in a 61-Pin Wire-Wrapped Bundle

R. Vaghetto, N. Goth, M. Childs, P. Jones, S. Lee, D. T. Nguyen, Y. A. Hassan (Texas A&M)

Particle Image Velocimetry Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle

N. Goth, M. Childs, P. Jones, S. Lee, D. T. Nguyen, R. Vaghetto, Y. A. Hassan (Texas A&M)

Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle

N. Goth, P. Jones, M. Childs, S. Lee, D. T. Nguyen, R. Vaghetto, Y. A. Hassan (Texas A&M)

CFD Verification and Validation of Wire-Wrapped Pin Assemblies

Daniel J. Leonard, R. Brian Jackson, K. Michael Steer, Tom Reeves (TerraPower), Nate Salpeter (AER Consulting)

Nek5000 Large-Eddy Simulations for Thermal-Hydraulics of Deformed Wire-Wrap Fuel Assembles

Aleksandr V. Obabko, Elia Merzari, Paul F. Fischer (ANL)

Challenges in Computational Tools for Reactor Thermal Hydraulics-Panel

Two-Phase Flows-I

Characterization of Impedance Void Meter Performance in Two-Phase Flow Measurement

Zhuoran Dang, Peng Ju, Yang Zhao, Xiaohong Yang, Robert Bean, Mamoru Ishii (Purdue Univ)

Local Measurement in Annular Flows using a Two-Sensor Droplet-Capable Conductivity Probe

Qingzi Zhu (Purdue Univ), Joshua P. Schlegel (Missouri Univ Sci Tech), Xiaohong Yang (Purdue Univ), Yang Liu (Virginia Tech), John R. Buchanan (Bechtel Marine Propulsion Corp.), Mamoru Ishii (Purdue Univ)

A Semi-Empirical Correlation for Counter-Current Flow Limitation in a Vertical Pipe

Katsuya Mori, Kosuke Hayashi, Shigeo Hosokawa, Akio Tomiyama (Kobe Univ)

Comparison of 3-D Bubble Reconstruction Algorithms

Yucheng Fu, Yang Liu, (Virginia Tech)

Image Analysis for Plug Bubbles in Horizontal Flow

Adam Rau, Ran Kong (Penn State), Stephen Bajorek (NRC), Kirk Tien, Chris Hoxie (NRC)

X-Ray Spectral Analysis for Void Fraction Measurement

Kyle Song, Yang Liu (Virginia Tech)

Drift-Flux Analysis in Horizontal Two-Phase Flow

Ran Kong, Seungjin Kim (Penn State), Stephen Bajorek (NRC), Kirk Tien, Chris Hoxie (NRC)

Two-Phase Flows-II

Spacer Grid and Mixing Vanes Effects Study on Two-Phase Flow Using Bubble Tracking Simulations

Jun Fang, Igor A. Bolotnov (NCSU)

Interfacial Area Transport through Vertical-Downward Elbows in Air-Water Two-Phase Flow

S. Qiao, S. Kim, D. Mena (Penn State)

A Proposed Correlation for Critical Flow Rate of Steam/Water Flow

Yeon-Sik Kim, Hyun-Sik Park, Seok Cho, Ki-Yong Choi (KAERI)

General Thermal Hydraulics-I

Sensitivity Tests of Aluminum Precipitate Preparation Methods on Head Loss through Debris Beds on a Sump Screen

Saya Lee, Vasileios Kyriakopoulos, Suhaeb S. Abdulsattar, Rodolfo Vaghetto, Yassin A. Hassan (Texas A&M), Janet J. Leavitt (Alion Science & Technology Corp.)

Development and Verification of MATLAB Functions for Pressure Drop Estimation in Crossflow Tube Bundles

J. B. Haefner, L. B. Carasik, Y. A. Hassan (Texas A&M)

Mixed Effects Associated with Air Ingress in Graphite Channels

Daniel Gould, Hitesh Bindra (Kansas State Univ)

Vibration Analysis of Advanced Test Reactor Mini-Plate Hydraulic Test in the OSU HMFTF

G. D. Latimer, W. R. Marcum, T. K. Howard (Oregon State Univ), W. F. Jones, A. M. Phillips, N. E. Woolstenhulme (INL), A. W. Weiss (Oregon State Univ)

An Approach to Assessment of Added Mass for a Plate in a Channel

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

Comparison of Calculated and Experimental Flows and Pressures in the Orifice Flow Test Facility

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

SIT Makeup Effect on the Loss of Residual Heat Removal during Mid-loop Operation

Cheolwoo Kim, Yonghee Lee, Jongcheol Park (KEPCO E&C)

General Thermal Hydraulics-II

Measurement of the Radiative Absorption Coefficient of FLiNaK

Ethan S. Chaleff, Thomas E. Blue (Ohio State)

Evaluation for Effect of TRACE Spacer Grid Model on RBHT Reflood Tests

Byung Gil Huh (KINS), Stephen M. Bajorek, Chris L. Hoxie (NRC)

A Simulation of a Steam Generator Tube Rupture in AP1000 Nuclear Power Plant Based on RELAP5-MV

Eltayeb Yousif, Zhijian Zhang, Zhaofei Tian, Ju Hao-ran (Harbin Engineering Univ)

Numerical Study of Vortex Core in Turbulent Swirling Flow

Ari Hamdani, Hiroshige Kikura (Tokyo Inst Technol)

The Effect of Support Rod on Film Boiling Heat Transfer for Hot Metal Sphere in Subcooled Water

S. H. Yoon, H. C. No (KAIST)

Severe Accident Modeling and Experiments for Advanced Reactor Safety

Sodium Spray Fire Simulations using CONTAIN-LMR

Andrew Jordan Clark, Matthew Roy Denman (SNL)

Experimental Study of Molten Metallic Fuel Relocation in Sodium-Filled Fuel Structures

Taeil Kim, Dzmitry Habaruk, Craig D. Gerardi, Mitchell Farmer, Yoon Il Chang (ANL)

Validation of Advanced In-Pin Metallic Fuel Models of SAS4A

Aydin Karahan, Adrian M. Tentner (ANL), Seok-H. Kang (KAERI)

SAS4A Model Development for the Analysis of Postulated Severe Accidents in Metal Fuel Sodium Fast Reactors

A. M. Tentner (ANL), S. H. Kang (KAERI), A. Karahan (ANL)

Effects of Coolant Void Condition on Melt Fragmentation using Simulants in Initial Phase of Metal-Fueled SFR Severe Accident

Hyo Heo, Min Ho Lee (UNIST), Dong Wook Jerng (Chung-Ang Univ), In Cheol Bang (UNIST)

Validation Study in SAS4A Code in Simulated Mild TOP Condition

Kenichi Kawada, Tohru Suzuki (JAEA)

Subchannel Thermal-Hydraulic Analysis-I

CTF Parallel Performance Improvements

R. Salko (ORNL), S. Palmtag (Core Physics, Inc.), B. Collins (ORNL)

Improvement of Wall Drag Modeling Capabilities of CTF

Aysenur Toptan (NCSU), Robert K. Salko (ORNL), Maria Avramova (NCSU)

Assessment of the Cobra-TF Post-CHF Models using FEBA Experimental Data

Jorge Perez, Christophe Schneidesch (Tractebel ENGIE), Javier Jimenez (KIT)

Advances in Fuel Rod Modeling in Subchannel Thermal-Hydraulic Codes

Aysenur Toptan, Maria Avramova (NCSU)

Towards a Neutronic and Thermal-Hydraulic Safety Analysis of PWR Fuel bow with SIMULATE5 and COBRA-TF

M. Seidl, A. Wensauer, D. Janin (E.ON Kernkraft GmbH), L. Belblidia (Studsvik Scandpower)

Comparison of Subchannel and Averaged Channel Thermal-Hydraulic Descriptions on Coupled Pin-By-Pin Neutronic Calculations

Adrian Sabater, Diana Cuervo, Santiago Sánchez-Cervera (UPM)

Integration and Coupling of ATHLET, CTF and DYN3D on the Salomé Platform-Application to a MSLB Transient

Yann Perin, Kiril Velkov (GRS)

Characteristics of Axial Power Shape and Flow Field at Low Flow Condition

Chong Kuk Chun, Beomjun Jang, Hyeongseog Kim, Joo Il Yoon, Hae-seuk Woo (Kepco Nuclear Fuel)

Subchannel Thermal-Hydraulic Analysis-II

Uncertainty Analysis of CTF for the Uncertainty Analysis in Modeling Benchmark

Nathan Porter (Penn State), Maria Avramova (NCSU)

CFD-Informed Spacer Grid Models in the Subchannel Code CTF

Taylor Blyth (Penn State), Robert Salko (ORNL), Maria Avramova (NCSU)

Critical Heat Flux Model Improvement in CTF for Natural Circulation Type Reactors

Caleb Jernigan (Penn State), Jordan Rader (Holtec International), Maria Avramova (NCSU)

Large Eddy Simulation and Direct Numerical Simulation

Single Bubble Drag Force Evaluation in Turbulent Flow based on DNS Results

Jinyong Feng, Igor A. Bolotnov (NCSU)

Single-Bubble Flow Boiling Phenomena-Interface Tracking Simulation

Mengnan Li, Igor A. Bolotnov (NCSU)

Two-Phase Flow Regime Transition Study using Level-Set Method

Matthew D.  Zimmer, Igor A. Bolotnov (NCSU)

DNS Study of Supercritical CO₂ Flow using Spectral Element Code Nek5000

Haomin Yuan, Elia Merzari, Yiqi Yu (ANL)

Large Eddy Simulations for a Helical Coil Steam Generator

J. K. Lai (Texas A&M), E. Merzari (ANL), S. J. Lee, M. Delgado, S. Lee, Y. A. Hassan (Texas A&M)

Simulations of a Helical Tube Bundle in Cross-Flow for Application to Flow-Induced Vibration

Adam Kraus, Haomin Yuan, Elia Merzari (ANL)

Experimental Thermal Hydraulics-I

Finding MP and CP using Ultrasonic Velocity Profile on Rectangular Twin Jets

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

A Radiotracer Assessment of Pulsatile Flow

Nitant Patel, Cody Wiggins, Arthur Ruggles (Univ of Tennessee, Knoxville)

Mapping Turbulent Flow around a Rod Bundle Induced by a 5x5 PWR Mixing Vane Grid using Particle Tracking Velocimetry

Carlos Estrada-Perez, Nasan Tsengeg, Ezra Hein, Yassin A. Hassan (Texas A&M)

Distributed Temperature Sensing within a 19-pin Wire-Wrapped Fuel Bundle Model

S. Lomperski, N. Bremer (ANL)

The Dynamic Response of a Wire-Wrapped Pin-A New Experimental Method

C. A. Nixon, W. R. Marcum (Oregon State Univ), K. M. Steer, R. D. Widdle, R. B. Jackson (TerraPower), A. Weiss (Oregon State Univ)

Development of TDLAS for Water Vapor Concentration Measurement during VHTR Steam Ingress

Michael C. Button, Philippe M. Bardet (George Washington Univ)

Experimental Study of the Downstream Effect of LOCA-Generated Debris on the Pressure Drop of Fuel Assembly

Weiqian Zhuo, Fenglei Niu, Zhangpeng Guo, Da Wang (North China Electric Power Univ)

Overview of the Salt at WAll Thermal ExcHanges (SWATH) Experiment

P. R. Rubiolo, M. Tano Retamales, J. Giraud, V. Ghetta (LPSC)

Analysis on the Heat Transfer Phenomena Inside the Scaled-Down VHTR RCCS Riser Experiment

Dong-Ho Shin, Sin-Yoeb Kim (Seoul Natl Univ), Chan-Soo Kimm (KAERI), Hyoung Kyu Cho, Goon-Cherl Park (Seoul Natl Univ)

Experimental Thermal Hydraulics-II

Experimental and CFD Analysis of Condensation with Non-Condensable Gas in Multi-Tubes

Do Yun Kim, Hee Cheon No (KAIST), Byong Guk Jeon (KAERI)

Experimental Study for Two Phase Flow Instability in the PCHE Type Steam Generator in SMR

Chang Wook Shin, Hee Cheon No (KAIST)

A New Empirical Correlation for Condensation Heat Transfer Coefficient of Air-Steam Mixture on a Vertical Tube

Yeon-Gun Lee, Yeong-Jun Jang, Un-Ki Kim (Jeju National Univ)

Effect of Local Void Fractions on Subcooled Boiling Oscillations in Natural Circulation Boiling Loop

Arnab Karmakar (BIT), Runa Dey (ISM), Swapan Paruya (NIT)

Uncertainty, Scaling and Global Sensitivity Methods in Thermal Hydraulics

RISMC Analysis Framework in Response to Proposed 10 CFR 50.46c Rulemaking

Hongbin Zhang, Ronaldo Szilard, Ling Zou, Haihua Zhao (INL)

SMR Re-Scaling and Modeling for Load Following Studies

K. Hoover, Q. Wu, (Oregon State Univ), S. Bragg-Sitton (INL)

Best-Estimate-Plus-Uncertainty-Informed Deterministic Safety Evaluation

R. P. Martin (BWX Technol)

ROM-Based Subset Selection Algorithm for Efficient Surrogate Modeling

Yeni Li, Hany Abdel-Khalik (Purdue Univ)

Uncertainty Quantification by Monte Carlo Analysis using CFD Simulations for GEMIX Benchmark Activities

A. M. Krueger, F. S. Sarikurt, L. B. Carasik, Y. A. Hassan (Texas A&M)

Sensitivity Analysis of OECD ATLAS A5.1 Test using MARS-KS Code

Yusun Park, Byoung-Uhn Bae, Kyoung-Ho Kang, Ki Yong-Choi (KAERI)

Sensitivity Analysis of Passive Heat Removal Capability of FHR based on Efficient Surrogate Model and GenFlow

Zhangpeng Guo, Yiping Luo, Fenglei Niu (North China Electric Power Univ)

Young Professional Thermal-Hydraulics Research Competition-I

Modeling of Two-Phase Flow around Spacers with Mixing Vanes in Reactor Rod-Bundles

B. M. Waite (RPI), D. R. Shaver (ANL), M. Z. Podowski (RPI)

High Resolution Measurements Reveal Transient Boiling Phenomena under Exponential Heat Inputs

Guanyu Su, Matteo Bucci, Thomas McKrell, Jacopo Buongiorno (MIT)

CFD-Grade Experiments Addressing Thermal Fatigue in Nuclear Reactor Branch Lines

J. R. Downing, V. Petrov, A. Manera (Univ of Michigan)

Improved Understanding toward Sliding Bubble Effect on Wall Heat Transfer in Subcooled Boiling Flow

Junsoo Yoo (INL), Carlos E. Estrada-Perez, Yassin A. Hassan (Texas A&M)

Simulation of Boiling Flow in a Helical Coil using a Homogeneous Equilibrium Model with the Nek-2P CFD Code

Dillon R. Shaver, Prasad Vegendla (ANL), W. David Pointer (ORNL), Adrian M. Tentner, Elia Merzari (ANL)

Modeling of a Passive Endothermic Reaction Cooling System

Nathan R. Murray, Mitchell E. Sailsbery, Samuel E. Bischoff, Matthew J. Memmott (Brigham Young Univ)

Dakota Uncertainty Quantification Methods Applied to the CFD Code Nek5000

Marc Olivier G. Delchini, Emilian L. Popov, David W. Pointer (ORNL)

Young Professional Thermal-Hydraulics Research Competition-II

A Study of Physics-Informed Deep Learning for System Fluid Dynamics Closures

Chih-Wei Chang, Nam Dinh (NCSU)

Verification and Validation of CFD Simulations Involving Twin Rectangular Jets using Steady RANS in Star-CCM+

L. B. Carasik, H. Wang, Y. A. Hassan (Texas A&M)

Thermal-Hydraulics of Severe Accidents

Analytical Models for Terry Turbine Nozzle

Haihua Zhao, Ling Zou, Hongbin Zhang, James O'Brien (INL)

Development of Accident Tolerant Fuel Options for Near Term Applications: Fuel Performance Modeling under Transient/Severe Accidents by MELCOR: PART I: Benchmark for SURRY: Short Term Station Black Out (STSBO)

Jun Wang, Michael L. Corradini, Troy Haskin (Univ of Wisconsin, Madison)

Pressure Drop-Flow Rate Curves for Single Phase Steam in Steam Generator U-Tube during Severe Accidents

Douglas A. Fynan, Kwang-Il Ahn (KAERI)

Thermo-Mechanical Analysis of SBLOCA with Loss of One Safety Injection System using SCDAP/RELAP5

Tae Hyun Chun, Wang-Kee In (KAERI), Tae-Wan Kim (Incheon National Univ)

Roles of Regulatory Organizations-Panel

Your Role in ANS National Committees-Panel

ANS Congressional fellowship-Panel

Potent Policies: Understanding ANS Position Papers-Panel

Nuclear Politics: Advocacy-Panel

Knowledge Transfer and Retention-Panel

Proposal Writing 101-Panel

ANS Standards and You-Panel

Student Conference Proposal Writing-Panel