Winter Meeting 2015 / Volume 113

ANS Officers

Meeting Officials, National Program Committee

Full Issue 1

Full Issue 2

Opening Plenary: Nuclear: The Foundation of Sensible Policy for Energy, Economy, and the Environment

ANS President’s Special Session

Enhancement of Risk-Informed Decision Making Against External Natural Events—Major Issues and R&Ds for Enrichment–Panel

General Chair’s Session

Nuclear Power Under the Clean Power Plan–Panel

Latest Advancements in Aerospace Nuclear Science and Technology

Americium Oxide Space Radioisotope Power Systems: Cerium-Neodymium Oxide Surrogate Studies

Emily Jane Watkinson, Richard Ambrosi, Hugo Williams (Univ of Leicester), Mark Sarsfield, Keith Stephenson (NNL)

The Importance of Doppler Broadened Cross Sections in Nuclear Thermal Rocket Design

Vishal Patel (Center for Space Nuclear Research, Texas A&M)

SCCTE: An LEU NTP Concept with Tungsten Cermet Fuel

Michael Eades (Ohio State, Center for Space Nuclear Research), Wesley Deason (Center for Space Nuclear Research), Vishal Patel (Center for Space Nuclear Research, Texas A&M)

Nuclear Fission: A Reliable and Clean Energy Source, Essential to Sustainable Development and to Reducing GHG Emission–Panel

Decommissioning and Environmental Sciences: General

Decommissioning Waste Classification of Bioshield Concrete for CANDU Reactor

Young-kyu Jung, Chang Lak Kim (KEPCO)

An Assessment System to Reduce Abnormal Hazards from Human Errors in Virtual Decommissioning Environments

KwanSeong Jeong, ByungSeon Choi, JeiKwon Moon, Dongjun Hyun, Jonghwan Lee, IkJune Kim, GeunHo Kim (KAERI)

The Status and Prospect of Regulatory Procedures for Permanently Shut-down Nuclear Power Plants in Korea

Yong Ki Chi, Chang-ju Lee, Bong Hyun Kim (Korea Inst Nucl Safety)

Nuclear Security Risk Analysis in Nuclear Power Plant Decommissioning Phase

Mbazor Jeremiah Chinonso, David S. Kessel (KEPCO)

Artificial Neural Network for Prediction of ⁹⁰Sr Soil to Plant Transfer Factor

Bary N. da Silva, Anna Karla G. dos Santos, Márcio Henrique da Silva, Carlos A. S. Lima Jr (IEN/CNEN),  J. C. Wasserman  (REMADS-UFF), Antonio Carlos de A. Mol, Celso Marcelo F. Lapa, Maria Angélica, V. Wasserman (IEN/CNEN)

Decommissioning Regulatory Requirements for Nuclear Power Plants–Panel

Focus on Communications: Communicating with Policy Makers–Panel

Focus on Communications: Meet the Media–Panel

Student Design Competition

Sodium-Cooled Integral Supercritical Carbon-dioxide Reactor (SCISCOR)

Kazi Ahmed, Ian Jentz, Richard Rolland (Univ of Wisconsin, Madison)

Production of ⁹⁹Mo Using A Photon-Neutron Interaction With ¹⁰⁰Mo Targets

Matthew Schaper, Eden Marroquin, Talal Harahsheh, Miltiadis Kennas, Yousif Almaazmi, Gamal Akabani (Texas A&M)

Neutron Activated Fluoride Salt Test Loop at The Ohio State University

Max Chaiken, Andrew Clark, Brian Cohn, James Cutright, Michael Kurth, Richard Shawger, Raymond Cao (Ohio State)

Zero Knowledge Active Interrogation of Nuclear Warheads

Crystal Green, Brianne Heisinger, Kyle Kondrat, Matthew Krupcale, Jennifer Nguyen (Univ of Michigan)

Innovations in Fuel Cycle Research—A Student Competition

Controlled Crystallization of Non-radioactive Salts from Legacy Nuclear Waste

Daniel Griffn, Martha A. Grover, Yoshiaki Kawajiri, Ronald W. Rousseau (Georgia Tech)

Electrochemical Monitoring of Nuclear Material in Molten Salts

Devin Rappleye, Milan Štika, Michael F. Simpson (Univ of Utah)

Functionalization and Oxo Ligand Substitution of Uranyl (UO2²⁺) via Reductive Silylation

Elizabeth A. Pedrick, Guang Wu, Trevor W. Hayton (Univ of California, Santa Barbara)

Program Optimization and Improved Workflow Synthesis for the OpenMOC Neutron Transport Code

William Boyd, Samuel Shaner, Benoit Forget, Kord Smith (MIT)

Irradiation Accelerated Corrosion of 316L Stainless Steel in PWR Conditions

Stephen S. Raiman, Gary S. Was (Univ of Michigan)

Hedging Strategies in Fuel Cycle Decision-making

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

Education and Training: General—I

Regional, Educational and Strategic: the Gulf Nuclear Energy Infrastructure Institute (GNEII) in Year 5

Adam D. Williams (SNL), Alexander Solodov (Khalifa Univ), David R. Boyle (Texas A&M), Amir H. Mohagheghi (SNL), Philip A. Beeley (Khalifa Univ)

Nuclear Security Curriculum Development for Academic Programs of Moroccan Universities-  Status and Progress

Oum Keltoum Aziza Bouhelal (ENSMR Engineering School)

Integral Nonproliferation Introductory Teaching and Learning (INITIAL) Module for Nuclear Engineering Courses at US Universities

Alexis Trahan, Rian Bahran (LANL), Catherine Snow (Sno Consulting LLC), Sean Morrell (INL)

Social Engineering: A Cybersecurity Threat

Jane LeClair (National Cybersecurity Institute)

Integrating Leadership into Nuclear Engineering Technology Degree Programs

Michael Johnson, Khamel Abdulai (Excelsior College)

Regional Cooperative Nuclear Engineering Summer Schools in Western Pacific Basin

T. K. Yeh, J. H. Liang, C. Shih (National Tsing Hua Univ)

Role of Nuclear in the Future Energy Production System (Scandinavia Case Study)

Kristiina Söderholm, Ville Lestinen (Fortum)

Education and Training: General—II

Modernizing Computational Nuclear Engineering Education in the Open

Kathryn Huff (Univ of California, Berkeley), Anthony M. Scopatz (Univ of South Carolina)

Answering the Scientific National Security Call in Nuclear Forensics: The Prairie View A&M University Approach to the Nuclear Forensics for Minority Serving Institutions Partnership

Royal Elmore (Texas A&M), Irvin Osborne-Lee, Richard Wilkins, Brad Gersey (Prairie View A&M Univ), Craig Marianno (Texas A&M)

A Simple Neutron-Physics Game to Assist Conceptual Learning of Nuclear Engineering

Robert W. Carlsen, Matthew J. Gidden (Univ of Wisconsin)

Static and Dynamic Representation of Radiation Fields in Virtual Models Using Unity-3D and Oculus

Justin Joseph, Abhiniti Mahendrakar, Daniel Chun (Univ of Illinois), Ye Li (Johns Hopkins Univ), Gavin Mattingly, Eric Riewski, Nabeel Y. Rizwan (Univ of Illinois), Yoshinori Satoh (Toshiba Corp), Quansheng Tan, Xuefeng Zhu, Rizwan-uddin (Univ of Illinois)

A 3D, Interactive and Virtual Dose Minimization Game for Education and Training

Gavin Mattingly, Eric Riewski, Quansheng Tan, Daniel Chun, Rizwan-uddin (Univ of Illinois)

Patents for Nuclear Professionals–Panel

The Importance of Professional Engineering Licensure in the Nuclear Industry–Panel

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

Development of Creep-Dominant Creep-Fatigue Tests for Alloy 617

Fraaz Tahir, Yongming Liu (Arizona State Univ)

Seismic Anchorage of Dry Storage Casks

Joel E. Parks, Chris P. Pantelides, Luis Ibarra (Univ of Utah), David Sanders (Univ of Nevada, Reno)

Temperature Effects on Piezoelectric Active Sensors

Linlin Ma, Howden Stephen, Lingyu Yu (Univ of South Carolina)

Effect of Helium Pre-implantation on Void Nucleation and Growth in HT9

Anthony M. Monterrosa, Zhijie Jiao, Gary S. Was (Univ of Michigan)

Comparison of Shaking Table Experimental Results for Different Aspect Ratios of Dry Storage Casks

Taylor M. Nielsen, A. Farghal Maree, David H. Sanders (Univ of Nevada, Reno)

Characterization of Thermo-mechanical Properties of the Nickel Based Super Alloy

Yang Zhang, Philipp Seiler, Vikas Tomar (Purdue Univ)

Investigation of Accident Thermal Effects on Seismic Performance

Saahastaranshu R. Bhardwaj, Kadir C. Sener, Amit H. Varma (Purdue Univ)

Decoupling the Functional Requirements of an Adsorbent for Harvesting Uranium from Seawater through the use of Shell Enclosures

Maha N. Haji (MIT), Charles Vitry (Univ of Cambridge), Alexander H. Slocum (MIT)

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

Multiscale Measurements on a Turbulent Jet and Refractive Index Matching for a Buoyant Jet in a Stratified Environment

Amy B. McCleney, Philippe M. Bardet (George Washington Univ)

Experimental Modal Analysis and Static Testing for Numerical Validation of Unirradiated Fuel Rods

Shokoufeh Zargar, Ricardo A. Medina (Univ of New Hampshire), Luis Ibarra (Univ of Utah)

Kriging-based Surrogate Models for Calibration of Multiphysics Fuel Performance Simulations

Nghia T. Nguyen, Michael P. Rose, Thomas J. Downar (Univ of Michigan)

Ab-initio Molecular Dynamics Study of the Solubility and Diffusion Coefficient of Cerium in Liquid Sodium

Xiang Li, Adib Samin, Jinsuo Zhang (Ohio State Univ)

Development of Modern CANDU PHWR Cross-Section Libraries for SCALE

Nathan T. Shoman, Steven E. Skutnik (Univ of Tennessee, Knoxville)

Hot Standby State Observers for Sensor Fault-Tolerance in Small Modular Reactors

Christopher J. D’Angelo, Daniel G. Cole (Univ of Pittsburgh)

GCFR-PROTEUS Experimental Program Benchmark Analysis

Gareth R. Newman, Kelly A. Jordan (Univ of Florida), Gregory Perret (Paul Scherrer Institut)

In-Core Neutron Measurement System for Pulsed TRIGA Reactor Experiments

Sophit Pongpun (Univ of Regina), Marvin L. Adams (Texas A&M), Thomas J. Conroy (Univ of Regina)

International Perspective of Electrochemical Recycling–Panel

Re-Establishing Plutonium-238 Production in the United States

Enabling Space Missions with Radioisotope Power Systems

Rebecca Onuschak (DOE)

Re-establishing the Supply of Plutonium-238

R. M. Wham, D. W. DePaoli, R. W. Hobbs (ORNL)

Potential Improvements to ²³⁸Pu Production Targets for the High Flux Isotope Reactor

R. W. Hobbs, D. Chandler (ORNL), C. J. Hurt (Univ of Tennessee, Knoxville), J. D. Freels, R. S. Owens, C. D. Bryan, R. W. Wham (ORNL)

Verification of the ²³⁸Np Fission Cross Section for HFIR ²³⁸Pu Production

Riley D. Hunley (ORNL), Justin R. Knowles (Univ of Tennessee, Knoxville), David C. Glasgow (ORNL)

The Role of the Department of Energy in Assembly, Test, and Launch Operations to Support a Nuclear-Enabled NASA Mission

Stephen Guy Johnson, Kelly L. Lively, Carla C. Dwight (INL)

Radioisotope Power Systems Launch Safety Process

Daniel J. Clayton, Ronald J. Lipinski (SNL), Ryan D. Bechtel (DOE)

Idaho National Laboratory: Improving Equipment Reliability and Increasing Capability

Kelly L. Lively, Eric S. Clarke, Stephen G. Johnson, Carla C. Dwight (INL)

Collaborative R&D for Future Nuclear Energy–Panel

Updates on Nuclear Waste Repository Projects

Recovery of the Waste Isolation Pilot Plant following the February 2014 Underground Release Event

Dana Bryson (US DOE, Carlsbad Field Office)

The French Geological Disposal Project, Cigéo

Gérald Ouzounian (ANDRA)

Status and Prospects of LILW and SNF Management in Korea

Jong-In Lee (Korea Radioactive Waste Agency)

Mechanical Analysis of Wheeled Canisters and Slant-path Boreholes for Disposal of Nuclear Spent Fuel

Roberto Formento Cavaier (Politecnico di Torino), Michael J. Driscoll (MIT)

Thermal Analysis for DWPF Glass Waste Storage Building Double Stacking

J. E. McAllister, Jr., M. R. Yeung, P. A. LaVigne, D. C. Thoman, J. E. Owen (AECOM URS Professional Solutions)

Progress in U.S. DOE’s Fuel Cycle R&D Program–Panel

Public Perception of Risk: Strategies to Address the “Perception Gap” with Nuclear Technologies–Panel

Integrated Spent Nuclear Fuel Management Analysis Capabilities—I

ORIGAMI: A New Scale Interface For Fuel Assembly Characterization With ORIGEN

Steven E. Skutnik (Univ of Tennessee, Knoxville), Mark L. Williams, Robert A. Lefebvre, William A. Wieselquist (ORNL)

A Proposed Spent Nuclear Fuel Storage and Transportation Licensing Approach Using As-loaded Analysis

Kaushik Banerjee, John M. Scaglione, John C. Wagner (ORNL)

Shielding Analysis Capability of UNF-ST&DARDS

Georgeta Radulescu, Robert A. Lefebvre, Kaushik Banerjee, Paul L. Miller, John M. Scaglione (ORNL)

Evaluation of Simplified Models for Estimating Public Dose from Spent Nuclear Fuel Shipments

Kevin John Connolly, Georgeta Radulescu (ORNL)

Containment Analysis Capability of UNF-ST&DARDS

Georgeta Radulescu, Robert A. Lefebvre, Paul L. Miller, Adam B. Thompson, Kaushik Banerjee, John M. Scaglione (ORNL)

Thermal Modeling Sensitivities with COBRA-SFS for Vertical Dry Casks with Limited Internal Convection

Kevin R. Robb (ORNL)

Integrated Spent Nuclear Fuel Management Analysis Capabilities—II

IAEA Project on Research Reactor Spent Fuel Management Options

Frances M. Marshall, Stefan J. Mayer (IAEA)

Spent Fuel Dissolver Predictive Modeling: I. Application of the Adjoint Sensitivity Analysis Methodology for Nonlinear Systems with Operator-Type Responses

Dan G. Cacuci (Univ of South Carolina), James J. Peltz, Aurelian F. Badea (KIT), Madalina C. Badea (Univ of South Carolina)

Spent Fuel Dissolver Predictive Modeling: II. Uncertainty Reduction via Experimental Data Assimilation

James J. Peltz, Aurelian F. Badea (KIT), Madalina C. Badea, Dan G. Cacuci (Univ of South Carolina)

Modernization of the Characteristics of Potential Repository Wastes Database

Josh Peterson, Bret van den Akker (ORNL)

A Methodology for Fuel Assembly Design Characterization

Justin B. Clarity, Kaushik Banerjee, John M. Scaglione (ORNL)

Recycle and Reuse of Used Nuclear Fuel Resources

R&D Progress on Recovery/Recycle of Zirconium from Used Fuel Cladding

E. D. Collins, Guillermo Daniel DelCul, B. B. Spencer, R. R. Brunson, R. D. Hunt (ORNL)

Purification of Zirconium Tetrachloride (ZrC_l4) from UNF Cladding – A Progress Report

Craig Barnes (Univ of Tennessee, Knoxville), Guillermo Daniel DelCul (ORNL), David F. McLaughlin (Westinghouse)

Opportunities to Reuse and Recycle Redundant Radioisotopes

Tim Tinsley, Dan Mathers (NNL)

Laser-Induced Breakdown Spectroscopy (LIBS) of Lanthanides in Solid LiCl-KCl Salt Samples

K. C. Bryce, A. N. Williams, S. H. Kim, S. Phongikaroon (VCU)

Fuel Cycle and Waste Management: General—I

Plutonium Disposition R&D within the United Kingdom

Fiona Rayment, Daniel Mathers, Tim Tinsley (NNL)

Investigation of Economics of Nuclear Fuel Cycle Options in the Republic of Korea

Seok-ki Cho, Man-sung Yim (KAIST)

Utility Fuel Assembly Qualification Evaluation for Transport Cask Design

Michael Smith, Brad Crotts (AREVA), Jay Verbos (Duke Energy), Sven Bader (AREVA)

A Hybrid Optimization Method for Loading Pattern Search Used in COSINE Package

Jincheng Su, Changhui Wang, Su Wang, Hui Yu, Yixue Chen (State Nuck Power Software Development Center)

Preliminary Physics Analysis of the Accident Tolerant Fuels Loop Experiment

Wilson M. Cowherd (INL)

Development of Attribute Framework and Tool to Support Evaluation of Attributes of Advanced Nuclear Systems

Andrea Resch Gardiner, Steven Krahn, Timothy Ault, Bethany Burkhardt, Allen Croff (Vanderbilt Univ), Andrew Sowder (EPRI)

Adsorption of Volatile Iodine from Off-Gas Stream using ETS-10 Supported Hollow Carbon Nanosorbent

Sachin U Nandanwar, Kai Coldsnow, Michael Green, Vivek Utgikar (Univ of Idaho),  Piyush Sabharwall (INL), D Eric Aston (Univ of Idaho)

Electrochemical Detection and Analysis of a Molten LiCl-KCl Eutectic Containing Multiple Lanthanides

Seunghyun Kim, Dalsung Yoon, Supathorn Phongikaroon (VCU)

Encapsulation of Graphene-Based Iodine-129 Sorbents Using Spark Plasma Sintering

Spencer M. Scott, Tiankai Yao, Jie Lian (RPI)

Fuel Cycle and Waste Management: General—II

Managing Stakeholder Acceptance for Socially Controversial Projects

Michael Golay, Adam D. Williams (MIT)

Performance Specifications for Standardized Transportation, Aging, and Disposal Canister Systems

A. A. Alsaed (Enviro Nuclear Services), J. A. Blink (Beckman and Associates), J. J. Jarrell, R. L. Howard (ORNL), E. L. Hardin, C. R. Bryan (SNL)

Benefits of Thermal Energy Storage at Nuclear Plants Using ERCOT as Case Study

Rachel Morneau, Erich Schneider (Univ of Texas at Austin), Charles Forsberg (MIT)

Thermal Analysis for wheeled Canisters and Slant-path Boreholes for Disposal of Nuclear Spent Fuel

Roberto Formento Cavaier (Politecnico di Torino), Michael J. Driscoll (MIT), Massimo Zucchetti (Politecnico di Torino)

Thermal Resistance Reduction in Cast Metal Filled Used Nuclear Fuel Canisters

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

A Socio-Economic Model of Multinational Nuclear Fuel Cycle

Viet Phuong Nguyen, Man-Sung Yim (KAIST)

Fast Finding of Fast Transitions to Fast Reactor Fuel Cycles with Cyclus

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

Portable Reactor Data Library Interpolation via Self-Describing ORIGEN Libraries

Nicholas C. Sly, Steven E. Skutnik (Univ of Tennessee, Knoxville), William A. Wieselquist (ORNL)

Analysis of BORAL^® Coupons from Zion Spent Fuel Pool

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

Fusion Energy—Devices and Applications

Estimation of Transient Effects of >2 mm Radii in Electrothermal Plasma Launchers for Fusion Fueling

Micah J. Esmond (Virginia Tech), A. Leigh Winfrey (Univ of Florida)

Thermal, Hydraulic, and Structural Analysis of the Wendelstein 7-X Divertor Scraper Element

Arnold Lumsdaine (ORNL), Emily Clark (Univ of Tennessee, Knoxville), Jean Boscary (Max Planck Institute for Plasma Physics), Kivanc Ekici (Univ of Tennessee, Knoxville), Jeffrey Harris, Dean McGinnis, Jeremy Lore (ORNL), Jӧrg Tretter (Max Planck Institute for Plasma Physics)

Design and Analysis of Miter Bends for High Power Electron Cyclotron Heating Transmission Lines

Arnold Lumsdaine, Greg Hanson (ORNL), Joseph Tipton (Lipscomb Univ), Alex Melin, Charles Schaich, Ira Griffith (ORNL)

Computational Design of Short Pulse Laser Driven Iron Opacity Measurements

Madison E. Martin (LLNL, Univ of Florida), Richard London (LLNL), Sedat Goluoglu (Univ of Florida), Heather Whitley (LLNL)

Activation Analysis of Lithium-based Ternary Alloys in IFE Blankets

Alejandra Jolodosky, Massimiliano Fratoni (Univ of California, Berkeley), Wayne Meier, James Demuth, Susana Reyes (LLNL)

Measurement and Modeling of Mechanical Behavior of V-SiC Interfacial Joints for Fusion Applications

Yomna H. Abdelmoaty, Gokul Vasudevamurthy (VCU)

Development of High Intensity D-T Fusion Neutron Generator (HINEG)

Yican Wu, Gang Song, Yongfeng Wang, Taosheng Li, Chao Liu, Jieqiong Jiang, FDS Team (Chinese Academy of Science)

Human Factors, Instrumentation, and Controls: General

Integrated Approach in Preparation for a Feedwater Control System Upgrade

Cristina Corrales, Fernando Raigoso, Luis Fernandez, Fernando Ortega (Tecnatom)

Safety Evaluation of Safety Grade Smart Transmitter in Nuclear Power Plants using Simulation Test Bed

Yeong Jin Yu (Korea Inst Nuclear Safety, Hanbat National Univ), Hyung Tae Kim, Jaeyul Choo, Choong Heui Jeong (Korea Inst Nucl Safety), Jae Heung Lee (Hanbat National Univ)

Estimation of Software CCFs for the Safety-Critical Digital Systems in Nuclear Power Plant

Koheun Kim, Jonghyun Kim (KEPCO)

Modelling Radiation-Induced Failures in FPGAs Using the Dynamic Flowgraph Methodology

P. McNelles, Z. C. Zeng, G. Renganathan (Canadian Nucl Safety Comm)

Simulation and Control of a Two-Loop Liquid Metal Reactor

Austin O’Connor, Jamie Coble (Univ of Tennessee, Knoxville)

Simulation of Advanced High Temperature Reactor Control System using MATLAB

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

Integrated Platform for Analysis and Design of Physical Protection System

Zou Bowen, Yang Ming, Song Mengchu (Harbin Engineering Univ)

Operator Interactions and Control Room Support Systems

Suggestion of Evaluation Method for Individual Competencies to Enhance Nuclear Safety Culture

Sang Min Han, Ar Ryum Kim, Poon Hyun Seong (KAIST)

Experimental Comparison to Validate a Situation Awareness Assessment of Human Operators Responding to Normal and Abnormal Indicators in Nuclear Power Plants

Seongkeun Kang, Poong Hyun Seong (KAIST)

Comparative Analysis of Communication Error between Conventional and Digitalized MCR Operators in NPPs

Seung Geun Kim, Ar Ryum Kim, Poong Hyun Seong (KAIST)

Multilevel Flow Modeling for Operating Procedure Tasks of CVCS

Song Mengchu, Yang Ming, Zou Bowen (Harbin Engineering Univ)

Nuclear Power Plant Condition Monitoring

Online Fault Diagnosis and Prediction of Condenser in Nuclear Power Plant

Wang Hang, Peng Minjun, Cheng Shouyu (Harbin Engineering Univ)

Condition Monitoring of Nuclear Power Plant with Hybrid Methods

Li Wei, Peng Minjun (Harbin Engineering Univ)

A High Confidence Signal Validation Technique for Sensor Calibration Assessment in Nuclear Power Systems

Anjali Nair and Jamie Coble (Univ of Tennessee, Knoxville)

Advanced Reactor System Modeling to Support Development of the Enhanced Risk Monitor

Xiaotong Liu, Chris Briere, Jamie Coble (Univ of Tennessee, Knoxville)

Development of Knowledge-based Software Tools for Defense-in-Depth Risk Monitor System

Zhanguo  Ma, Hidekazu Yoshikawa (Harbin Engineering Univ), Takashi Nakagawa (Prime Systems Laboratory, Co.)

Distributed Temperature Measurements using Optical Fiber in the OSU Nuclear Reactor

Brandon A. Wilson, Benjamin Reinke, Christian Petrie, Thomas E. Blue (Ohio State Univ)

Development and Demonstration of Inferential Flow Characterization Techniques for Novel Advanced Reactors

Ryan Tarver, Greg Meinweiser, Brian Cady, Belle Upadhyaya, Wes Hines, Jamie Coble (Univ of Tennessee, Knoxville)

Nuclear Techniques for Material Analysis

Fissile Material Assay Using Short-Lived Fission Product Measurements

Justin Knowles, Steven Skutnik (Univ of Tennessee), Roger Kapsimalis, David Glasgow (ORNL)

Use of PFTNA for On-Line Coal Analysis

Uner Colak (Istanbul Tech Univ), Nizametin Erduran (Istanbul S. Zaim Univ), Iskender A. Reyhancan (Istanbul Tech Univ)

Neutron Activation Analysis with a Monte Carlo Simulation for Kidney Stones

Huseyin Sahiner, Anjali Srivastava, Xin Liu (Missouri Univ of Science and Technology), Cynthia H. McCollugh (Mayo Clinic)

Experimental Performance of the Multi Isotop Process Monitor

Nathan Shoman, Jamie Coble (Univ of Tennesee, Knoxville), David Meier (PNNL)

Implementation of an FPGA-Based Digital Coincidence Doppler Broadening Spectrometer for PAS Measurements

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

Long-term 500 C Testing of High Temperature 4H-SiC Schottky Diode Alpha Particle Detectors for Pyroprocessing

Benjamin Reinke, Joshua Jerrell, Max Chaiken, Brandon A. Wilson, Thomas E. Blue, Wolfgang Windl, Bryan D. Esser, Lei Cao (Ohio State)

Advances in Radiation Detection and Measurement

A Convolution Method for Identification of Moving Radiation Sources

Thomas E. Albert (Dept of Homeland Security)

Sb-doped BiI3 – Developing the Next Room Temperature Spectrometer

Paul M. Johns (Univ of Florida), Mary Bliss (PNNL), Juan C. Nino (Univ of Florida)

Studying Environmental Effects on Radiation Detectors Response

Braden Goddard, George W. Hitt, Alexander A. Solodov (Khalifa Univ)

A Real-Time Personal Neutron Dosimeter using Microstructured Solid-State Neutron Detectors

A. Weltz, I. Bhat, R. Dahal, Y. Danon (RPI)

Uranium Enrichment Measurements Simulations Using MCBEND Monte Carlo Code for Nuclear Safeguards and Security Education

Alexander A. Solodov (Khalifa Univ, Gulf Nuclear Energy Infrastructure), Braden Goddard (Khalifa Univ)

Isotopes and Radiation: General

Domestic Production of ⁹⁹Mo Using a Superconducting Electron Linac

T. L. Grimm, S. S. Barnard, C. H. Boulware, A. K. Grimm, J. L. Hollister, E. S. Maddock, M. Mamtimin, V. N. Starovoitova (Niowave, Inc.)

Moderator Optimization in Neutron Backscattering Landmine Detection

Walid A. Metwally, Sara Y. Alawabdeh, Mohammed M. Ballaith (Univ of Sharjah)

Development of a Realistic Model for Optimizing Betavoltaic Battery Design

Tariq R. Alam, Mark A. Pierson (Virginia Tech)

Real-Time Digital Neutron Radiography and Tomography at the PULSTAR Reactor

A. Datta, A. I. Hawari (NCSU)

Detecting ²³³U Diversion using Antineutrinos

Oluwatomi A. Akindele, Eric B. Norman (Univ of California, Berkeley), Adam Bernstein (LLNL)

Radioactive Argon Measurements at the Nuclear Engineering Teaching Laboratory

S.R. Biegalski, E. Moll, E. Artnak (Univ of Texsas at Austin)

Accident Tolerant Fuel

High Temperature Testing of Geometrically Relevant, Nuclear Grade Silicon Carbide Joints

George M. Jacobsen, Hesham E. Khalifa, Yi Kearns, Oscar Guitierrez, Christian P. Deck (General Atomics)

Improvements to Coding of Lanthanide Behaviors in Metal Fuel

C. W. Arnold, Jack Galloway (NEN-5), N. Carlson (CCS-2 LANL), C. Unal (NEN-5)

Oxidation States of Advanced Steel Alloys Exposed to Super-Heated Water

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

Protection of Zirconium Fuel Cladding with Chromium Surface Coating

James Carr, Gokul Vasudevamurthy (VCU)

Thermal Shock Analysis of Silicon Composites for LWR Cladding

Pierre Guenoun, Gregory Daines, Thomas McKrell (MIT), Ed Lahoda (Westinghouse), Christian Deck (General Atomics), Mujid Kazimi (MIT)

Current Status of FeCrAl Alloys as an Accident Tolerant Cladding Alloy Class for Commercial Light Water Reactors

Kevin G. Field, Yukinori Yamamoto, Bruce Pint, Richard Howard, Lance L. Snead, Kurt A. Terrani (ORNL)

Fuel Performance Calculations for FeCrAl Cladding in BWRs

Nathan N. George, Ryan T. Sweet, G. Ivan Maldonado, Brian D. Wirth (Univ of Tennessee, Knoxville), Jeffrey J. Powers, Andrew Worrall (ORNL)

Nuclear Structural Materials

Full-Field Strain Measurements at Extreme Temperatures using Ultraviolet Digital Image Correlation (UV-DIC)

Ryan B. Berke (Utah State Univ)

Models of Multi-Layered Compositions of Steel Fuel Claddings for UO₂ Elements

A. I. Ksenofontov, E. I. Kurbatova, Alalaween Hamdi Abdel Ruhman (Moscow Engineering Physics Institute), N. A. Mould, J. L. Regens (Univ of Oklahoma)

A Fast Spectrum Neutron Source for Material Irradiation using a Superconducting Electron Linac

T. L. Grimm, S.S. Barnard, C. H. Boulware, A. K. Grimm (Niowave, Inc.), F. J. Harmon (Idaho Accelerator Center), J. L. Hollister, E. S. Maddock (Niowave, Inc.), S. A. Maloy (LANL), M. Mamtimin, V. N. Starovoitova (Niowave, Inc.), and K. A. Woloshun (LANL)

Diffusion Bonding of 316 SS Tube-to-Tube Sheet Joints using a Commercial Tube Expander

Nils Haneklaus, Rony Reuven, Cristian Cionea, Peter Hosemann, Per F. Peterson (Univ of California, Berkeley)

Development of Environmental Barrier Coatings for Operational Conditions of SiC Cladding in Light Water Reactors

C. Ang, J. Kiggans (ORNL), C. Kemery (NEO Industries), J. Thomson, Y. Katoh, Kurt Terrani (ORNL)

Comparison Between Thermal Aging And Low Dose Neutron Irradiation Effects On Ferrites In A Duplex Structure Stainless Steel

Zhangbo Li (Univ of Florida), Yiren Chen (ANL), Yong Yang (Univ of Florida)

Compact and Flexible Neutron Source for Fast and Fusion Neutron Irradiation Applications

G. Longoni, D. Wootan, K Burns, R. Gates, B. Schmitt (PNNL)

Demonstration of Advanced Manufacturing Techniques for Production of Nuclear Core Structures: Ultrasonic Additive Manufacturing of Hybrid Structures Resembling HFIR Control Plates

Kurt Terrani (ORNL), S. Suresh Babu (ORNL, Univ of Tennessee, Knoxville), Chris Bryan, James Kiggans, Daniel Pinkston (ORNL), Niyanth Sridharan, Maxim Gussev (Univ of Tennessee, Knoxville), Mark Norfolk (Fabrisonic LLC)

Overview of National Lab Facilities for Radioactive Material

Mechanical Testing and Post Irradiation Examination in the Wing 9 Hot Cells at Los Alamos National Laboratory

Tarik A. Saleh, Stuart A. Maloy, Matthew E. Quintana, Tobias J. Romero (LANL)

LAMDA: A Facility for Advanced Characterization of Irradiated Materials at Oak Ridge National Laboratory

Keith J. Leonard, Kevin G. Field, Chad M. Parish, Philip D. Edmondson, Maxim N. Gussev, Xunxiang Hu,  Chinthaka M. Silva, Anne A. Campbell, N.A.P. Kiran Kumar, Kurt A. Terrani, Jeremy T. Busby, Yutai Katoh (ORNL)

Radioactive Materials Characterization at the National Synchrotron Light Source-II

Lynne E. Ecker, David J. Sprouster, Eric Dooryhee (BNL)

Fuels and Materials Characterization Capabilities at the Idaho National Laboratory and the Center for Advanced Energy Studies

James I. Cole, Assel Aitkaliyeva (INL), Yaqiao Wu, Jatuporn Burns (BSU), Joanna Taylor (Univ of Idaho)

The Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory

Walter Luscher (PNNL)

Irradiation Assisted Stress Corrosion Cracking Testing Capability at INL

S. Teysseyre. J. H. Jackson, M. Heighes (INL)

Advanced Postirradiation Examination Facilities at the Idaho National Laboratory

Mitchell K. Meyer, Collin Knight (INL)

Argonne Capabilities for Radioactive Materials Characterization in the Irradiated Materials Laboratory (IML)

M.C. Billone, Y. Chen (ANL)

Nuclear Fuels, Performance Testing, and Disposition

Corrosion and Radiation Damage of Single Layer Coatings on Steel for High Level Waste Packages

Michael Fusco, Yasar Ay (NCSU), Abigail Casey (Univ of Florida), Mohamed Bourham (NCSU), Leigh Winfrey (Univ of Florida)

Evaluation of Mechanical Properties of Coated Steel for HLW Packages

Abigail H.M. Casey (Univ of Florida), Caroline A. Campbell (Virginia Tech), Michael A. Fusco, Mohamed A. Bourham (NCSU), A. Leigh Winfrey (Univ of Florida)

Status of the B-14 Experiment Modeling Using BISON

Pavel G Medvedev (INL)

Innovative Coating of Vanadium Carbide on the F/M Stainless Steel for Mitigating Fuel Cladding Chemical Interaction

Kookhyun Jeong, Shaosong Huang, Yong Yang (Univ of Florida)

Case Comparison between FRAPTRAN and BISON for an Idealized Reactivity-Initiated Accident of a Light Water Reactor Fuel

Rod, C. Folsom (Utah State Univ), P. Raynaud (NRC), A. Zabriskie (Oregon State), R. Williamson (INL), H. Ban (Utah State Univ), D. Wachs (INL)

Out-of-pile Study of Constituents Migration in U-Zr and U-Zr-Ce Alloys under Thermal Gradients

Yeon Soo Kim, T. Wiencek, E. O’Hare, J. Fortner (ANL), B. O. Lee, J. S. Cheon (KAERI)

Physical Property Model for Advanced Oxide Fuels

Masato Kato (JAEA), Kenneth J. McClellan (LANL)

MOX Fabrication and Performance

Sintering Behavior of (U,Ce)O₂ and (U,Pu)O₂

S. Nakamichi, S. Hirooka, T. Sunaoshi, M. Kato (JAEA), A. T. Nelson, K. J. McClellan (LANL)

Early-in-Life Fuel Restructuring Behavior of Am-bearing MOX Fuels

Kosuke Tanaka, Shinji Sasaki, Kozo Katsuyama, and Shin-ichi Koyama (JAEA)

Fuel Restructuring Behavior Analysis of MA-bearing MOX Fuels Irradiated in a Fast Reactor

T. Ozawa, Y. Ikusawa, M. Kato (JAEA)

Thermochemistry and Phase Equilibria of the U-Ce-O System

Jacob W. McMurray (ORNL)

Thermophysical Properties of (U,Ce)O₂±x

J. T. White (LANL), S. Hirooka, T. Murakami (JAEA), A. T. Nelson, K. J. McClellan (LANL), M. Kato (JAEA)

Evaluate The Thermal Conductivity of Off-Stoichiometry Cerium Oxide

Yuedong Wu, Yong Yang (Univ of Florida)

Transient Fuel Performance and Testing–Panel

Current Issues in Computational Methods–Panel

Transport Methods: Monte Carlo and Radiative Transfer

Analysis of α-Approximation For Nonlinear Radiative Transfer Problems

Pedram Ghassemi, Dmitriy Y. Anistratov (NCSU)

Improved Monte Carlo Tallying of Multi-Group Scattering Moments Using the NDPP Code

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

Deterministic Fission Matrix Acceleration of Monte Carlo Calculations

Steven Hamilton, Tom Evans (ORNL)

The Temperature Zoning Method for the On-the-Fly Thermal Scattering Sampling Procedure

Andrew T. Pavlou, Wei Ji (RPI)

Doppler Broadening by Linear Combination of Reference Temperature Cross Sections L2 Kernel Minimization Cross Section Temperature Interpolation Methods

Pablo Ducru, Colin Josey (MIT), Vladimir Sobes (ORNL), Benoit Forget, Kord Smith (MIT)

A Monte Carlo Algorithm for Fission Chain Analysis of Dynamic Stochastic Systems

Travis J. Trahan, Steven Nolen, Terry Adams, Jeremy Sweezy (LANL)

Uncertainty Quantification and Sensitivity Analysis Methods

Adjoint-Based Sensitivity Analysis for Flux Limited Diffusion

Kelli Humbird, Ryan McClarren (Texas A&M)

Improvement of the Fast Fourier Transform Based Method for Thermal-Hydraulic System-Code Accuracy Quantification

Tae Wook Ha (Pusan National Univ), Ki Yong Choi (KAERI), Jae Jun Jeong (Pusan National Univ)

Transport Methods: Deterministic

A High-Order Nonlinear Diffusion Acceleration for the S_NEquations Discretized with the Discontinuous FEM I: Theory and Numerical Results

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

A High-Order Nonlinear Diffusion Acceleration for the S_NEquations Discretized with the Discontinuous FEM II: Fourier Analysis

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

Fourier Stability Analysis of 1-D/1-D Fusion Method and 1-D/1-D Hybrid Method  in Two-Dimensional Transport Problems

Seungsu Yuk, Nam Zin Cho (KAIST)

Non-oscillatory Reweighted Least Square Finite Element Method for S_N Transport

Weixiong Zheng, Ryan G. McClarren (Texas A&M Univ)

Non-oscillatory Reweighted Least Square Finite Element for Solving P_N Transport

Weixiong Zheng, Ryan G. McClarren (Texas A&M Univ)

Solution of Neutron Transport Equation for Criticality Estimation  Using Lattice Boltzmann Method

Gaurav Agarwal (Nuclear Power Corp of India LTD), Suneet Singh (Indian Inst Technol Bombay), Hitesh Bindra (Kansas State Univ), Surendra Mishra (Nucl Power Corp of India LTD)

On-Node, Parallel Performance of 2-D Discrete-Ordinates Sweeps

Wenkai Fu, Jeremy A. Roberts (Kansas Sate Univ)

Computational Methods: General

Comparison of Novel Multiphysics Coupling Methods in MOOSE

Jaron P. Senecal, Wei Ji (RPI)

Heterogeneous Variational Nodal Methods for Eliminating the Control Rod Cusping Effect

Yunzhao Li, Yongping Wang, Hongchun Wu and Liangzhi Cao (Xi’an Jiaotong Univ)

Indirect Computation of Dominant Time-Eigenvalue of a Nuclear Reactor

Huayun Shen, Bin Zhong (Inst of Applied Physics and Computational Mathematics)

Leveraging Intel’s Embree Ray Tracing in the DAGMC Toolkit

Patrick C. Shriwise, Andrew Davis, Paul P. H. Wilson ( Univ of Wisconsin, Madison)

Special Panel Session—The Legacy of NCS Pioneer Joe Thomas

Data Analysis and Operations in Nuclear Criticality Safety

Reflector Worth of Dry Chemical and Powder Fire Extinguishing Agents

A. R. Wysong, B. S. Chapman (LANL)

ANSI/ANS-8.12 Revision:  Selection of MOX Critical Experiments and Preliminary Validation Results

Christopher S. Tripp, Debdas Biswas (LLNL)

A Note on Boundary Conditions and Sources for Analytical Benchmarks

Barry Ganapol (Univ of Arizona), Forrest Brown (LANL)

The 2015 Edition of the ICSBEP Handbook

John D. Bess (INL), Jim Gulliford (OECD NEA)

Results of Partially-Reflected Critical Experiments in Square-Pitched Arrays of Water-Moderated 6.9 Percent Enriched Fuel Rods

Gary A. Harms, John T. Ford, and Rafe D. Campbell (SNL)

Reactivity Worth Studies Associated with a Rossi-α Measurement System

George E. McKenzie, Theresa E. Cutler, Travis J. Grove, William L. Myers, Rene G. Sanchez (LANL)

Recent Nuclear Criticality Safety Program Accomplishments

New NCSP Contributions to ICSBEP and DICE

David Heinrichs (LLNL), Ian Hill (OECD/NEA)

Design of Two New Critical Experiments

C. Percher, S. Kim, D. Heinrichs (LLNL)

MCNP Progress and Performance Improvements

Forrest B. Brown, Jeffrey S. Bull, Michael E. Rising (LANL)

Analysis of Thermal Neutron Scattering In Polymethyl Methacrylate (Lucite)

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

SAMINT: A New Evaluation Tool to Perform Resonance Parameter Data Adjustments based on Integral Experiment Data

Vladimir Sobes, Luiz Leal, Goran Arbanas, Marco Pigni (ORNL)

The DOE Criticality Safety Support Group – A Retrospective Perspective

Fitz Trumble (URS Corporation), David Erickson (Savannah River Nuclear Solutions)

NDA Issues Affecting Nuclear Criticality Safety–Panel

ANS-8 Standards–Forum

Current Topics in Probabilistic Risk Analysis

Generation and Use of Reduced Order Models for Safety Applications Using RAVEN

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

Functional Failure Probability Estimation of Passive Cooling System in ACP1000 Using Surrogate Models

Chen Wang, Jingquan Liu, Yuyun Zeng (Tsinghua Univ)

On-Line Configuration Risk Management of NPP with RISMC

Anqi Xu, Zhijian Zhang (Harbin Engineering Univ)

Development and Application of Reliability and Probabilistic Safety Assessment Program RiskA5.0

Fang Wang, Jin Wang, Pengcheng Long, Liqin Hu, Shanqi Chen, Jiaqun Wang, Miao Nie, Dagui Wang, Run Yuan, Yinlong Xu, Yican Wu, FDS Team (Chinese Academy of Sciences)

A New Methodology to Evaluate Severe Accident Management Strategies Using Decision Tree

Moosung Jae, Yongjin Lee (Hanyang Univ), Dong Wook Jerng (Chung-Ang Univ)

The Revised IAEA Safety Guide on Accident Management - A Critical Review

George Vayssier (NSC Netherlands)

Nuclear Installations Safety: General

Facilitating International Licensing for Small Modular Reactors (World Nuclear Association)

Kristiina Söderholm (Fortum)

Applications of PCTRAN for URG Evaluations Under SBO Conditions in Chinshan BWR/4

T. Y. Wang, Y. T. Hsu, S. W. Chen (National Tsing Hua Univ)

Advanced Licensing and Safety Engineering Method - ADLAS™

Kristiina Söderholm, Pekka Nuutinen (Fortum)

Conceptual Design for a Primary Containment Capture System (PCCS)

Hyungjooh Na, Robert M. Field (KEPCO)

Development and Initial Validation of Core Meltdown Progression Accident Simulation Software (COMPASS)

D. H. Kim, J. H. Bae (KAERI), R. M. Podowski (Podowski Engineering Consulting), M. Z. Podowski (Podowski Engineering Consulting, RPI)

Transient Hydraulic Response of a PWR Steam Generator to a Feed Water Line Break

Jong Chull Jo (Korea Inst Nucl Safety)

Design Concept on the 4th and 5th Layers Defense-In Depth Risk Monitor to Cope with Severe Accident

Hidekazu Yoshikawa (Harbin Engineering Univ, Symbio Community Forum), Ming Yang, Zhijian Zhang (Harbin Engineering Univ)

Investigation of Foam-Based Removal of Gaseous Iodine

Irfan Younus, Man Sung Yim (KAIST)

The 2015 Dwight D. Eisenhower Award Special Session–Panel

Nuclear Data Needs for National Security–Panel

University Consortia for Nuclear Nonproliferation Research and Development–Panel

Rationalizing Recycling in a Nonproliferation World: An ANS Public Policy Track–Panel

Proliferation Risk and Sustainability of Nuclear Energy Systems–Panel

An Overview of the 2015 NPT Review Conference—Considerations for the Next 5 Years–Panel

Nuclear Nonproliferation Policy: General

Domestic New Nuclear Construction–Panel

All Energy–Forum

New Nuclear Construction Around the World—Status Report–Panel

Operations and Power: General

Development of a Simplified Estimation Method on Severe Accident Progression in PWR for Education

Shohei Otsuki, Tomohiro Endo, Akio Yamamoto (Nagoya Univ)

Impact of Firebrick Resistance-Heated Energy Storage (FIRES) on Electricity Prices in a Nuclear Renewable Grid

Daniel C. Stack, Charles Forsberg (MIT)

The Best Value Procurement by Applying the Plant Risk Information and Historical Data

Jinseok Yang, Sunkoo Kang (KEPCO)

Evaluation of Carbon Recycling Energy Process Driven by Nuclear Power

Yukitaka Kato (Tokyo Inst of Technol)

Benchmarking Of Coupling Approaches for Modeling of a Whole Nuclear Power Plant

Josh C. Pack, Zheng Fu, Fatih Aydogan (Univ of Idaho)

MTBF Estimation of a New Design RCP

Yang Ming, Lu Hongxin, Wang Wenlin, Yoshikawa Hidekazu (Harbin Engineering Univ)

Policy Issues for New Reactors, a Retrospective

Small Modular Reactors

Mk1 Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor Capital Cost Estimation

C. Andreades, P.F. Peterson (Univ of California, Berkeley)

Mk1 Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor Operating Cost Estimation

C. Andreades, P.F. Peterson (Univ of California, Berkeley)

Low Boron Concentration Small PWR Core Designs using Advanced Particle Burnable Poisons

Hoseong Yoo, Ser Gi Hong (Kyung Hee Univ)

Location Sensitivity Analysis of Small Modular Reactor Construction Cost

Giovanni Maronati, Bojan Petrovic, James W. Banner, Chelsea C. White III (Georgia Tech), Matthew H. Kelley, Jurie Van Wyk (Westinghouse)

Superconducting Subcritical Testbed for Near Term Demonstration of Small Modular Reactors

T.L. Grimm, S.S. Barnard, C.H. Boulware, A.K. Grimm, J.L. Hollister, E.S. Maddock, M. Mamtimin, and V.N. Starovoitova (Niowave, Inc.)

Impact of Regulatory Fee Structures on the Economic Viability of Small Modular Reactors

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

Small Modular Reactor Modeling Using Modelica for Nuclear-Renewable Hybrid Energy Systems Applications

Daniel Mikkelson, Chih-Wei Chang (NCSU), Sacit M. Cetiner, A. Lou Qualls (ORNL), J. Michael Doster, T. Nam Dinh (NCSU)

Advanced/Gen-IV Reactors—I

Optimization of Nuclear Steam Generation Systems via Multi-Parameter Sensitivity Analysis

Paul R. Wilding, Matthew J Memmott (BYU)

Optimizing Nuclear Energy at a Refinery

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

Design Optimization for Miniature Nuclear Reactors

Sal Rodriguez and David Ames (SNL)

Burnup Analysis of Accumulative Fuel Loading Scheme Pebble Bed Reactor with Optimum Fuel Composition

Irwan Liapto Simanullang, Toru Obara (Tokyo Inst of Technol)

Composition of ROX Fuel for High-Burnup Pebble Bed Reactor

Hai Quan Ho, Toru Obara (Tokyo Inst of Technol)

Application of the Melt and Refining Procedure to the CANDLE Reactor Concept

Julia Abdul Karim, Jun Nishiyama, Toru Obara (Tokyo Inst of Technol)

Mitsubishi Small Module High Temperature Gas-cooled Reactor “MHR-100” system design - An optimization study on MHR-100 Gas Turbine system (MHR-100GT)-

Isao Minatsuki, Sunao Oyama, Hiroki Tsukamoto, Masayuki Imoto (Mitsubishi Heavy Industries)

Mitsubishi Small Module High Temperature Gas-cooled Reactor “MHR-100” conceptual design - Conceptualization, Improvement and Evolution -

Isao Minatsuki, Sunao Oyama, Hiroki Tsukamoto, Masayuki Imoto (Mitsubishi Heavy Industries)

Advanced/Gen-IV Reactors—II

Design Optimization of a Fluoride Salt Cooled High Temperature Test Reactor Capable of Testing Different Salt Coolants

Joshua Richard, Benoit Forget, Charles Forsberg, Kord Smith (MIT)

A Model of Tritium Transport and Corrosion in Salt-Cooled Reactors

John Stempien, Ron Ballinger, Charles Forsberg (MIT)

Tritium Removal from Salt-Cooled Reactors Using Carbon

Charles Forsberg, John Stempien, Ron Ballinger (MIT)

Basis for a Demonstration Fluoride-Salt-Cooled High-Temperature Reactor

Charles Forsberg, Lin-wen Hu, Joshua Richard, Rebecca Romatoski, Benoit Forget, John Stempien, Ron Ballinger, Kaichao Sun, and David Carpenter (MIT)

Air-Brayton Systems with Salt, Sodium, and Helium Base-Load Reactors with Variable Electricity, Steam and Hot-Air Output

Charles Forsberg (MIT), Pat McDaniel (Univ of New Mexico)

Nuclear Air-Brayton Combined Cycles for Sodium Cooled Fast Reactors

Charles Forsberg (MIT), Pat McDaniel (Univ of New Mexico)

Advanced Nuclear Energy System Options to Provide Flexible, Dispatchable, Very-Low-Carbon Electricity

Daniel Curtis, Charles Forsberg (MIT)

Continuing the Commitment to Ethics–Panel

Radiation Protection and Shielding: Computational Methods and Applications

Radiological Toolbox 3.0.0

Nolan E. Hertel, Keith F. Eckerman (ORNL), Caspar Sun (NRC)

Virtual Reality-Based Simulation of ADS Spallation Target Maintenance

Tao He, Zihui Yang, Shaoheng Zhou, Jinbo Zhao, Tongqiang Dang, FDS Team (Chinese Academy of Sciences)

CADIS Weight Windows using a Memory Efficient Adapted Mesh Structure

Bojan Petrovic, Timothy Flaspoehler (Georgia Tech)

Developing a Mathematical Scheme to combine Single-Parameter Perturbation Results in Radiation Transport Calculations to Predict Joined Parameter Perturbations

Caroline L. Hughes, Aakanchha Chirayath, Sunil Chirayath (Texas A&M)

The Solid Angle for a Spherical Surface Source and a Detector with an Arbitrary Aperture

Jeffrey A. Favorite (LANL)

The Solid Angle for a Spherical Surface Source and a Point Detector

Jeffrey A. Favorite (LANL)

Federal Guidance Report 15: External Exposure to Radionuclides in Soil, Air, and Water

N. E. Hertel (ORNL, Georgia Tech), K. F. Eckerman, M. B. Bellamy (ORNL), C. E. Easterly (Easterly Scientific), R. W. Leggett (ORNL), J. C. Ryman (Private Consultant), D. J. Stewart (ORNL), M. Boyd (US EPA)

Radiation Protection and Shielding of Fusion and Fission Power Systems

Neutronics for Diagnostic Systems of ITER Port Plugs

A. Serikov (KIT), R. Barnsley, L. Bertalot, M. De Bock, R. O’Connor (ITER), U. Fischer (KIT), R. Thenevin (ITER)

Estimating Radionuclide Dose from Contaminated Surfaces of the Piping Systems at Nuclear Power Plants

A.I. Ksenofontov, E.I. Kurbatova, Alalaween Hamdi Abdel Ruhman (Moscow Engineering Physics Institute), N.A. Mould, J.L. Regens (Univ of Oklahoma)

Preliminary Analysis of Source Term and Consequence Assessment of Hypothetical Fuel Assembly Meltdown Accident for CLEAR-I

Tongqiang Dang, Ming Jin, Pengcheng Long, Chufeng Jin, Yican Wu, FDS Team (Chinese Academy of Sciences)

Coupling Of MCNP5 To ORIGEN To Support ATR NSUF Experiments

Joseph W. Nielsen (INL), G. Robert Odette (Univ of California, Santa Barbara), Michael Sprenger, Thomas Maddock (INL)

Radiation Protection and Shielding–Roundtable

Computational Tools for Radiation Protection and Shielding

MCNP Delayed-Particle Library – Release 5

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

Validation of MCNP6 for Electron Energy Deposition in Extended Media

D. A. Dixon, H. Grady Hughes (LANL)

PyNE: Usage for Automatic PARTISN Input File Generation from a CAD Geometry

Kalin R. Kiesling, Andrew Davis, Paul P.H. Wilson (Univ of Wisconsin, Madison)

Advanced Variance Reduction Techniques for Shielding Calculation in Monte Carlo Simulation Program SuperMC

Lijuan Hao, Huaqing Zheng, Xinmei Li, Bin Wu, Jing Song, Juping Hu, Yican Wu, FDS Team (Chinese Academy of Sciences)

The MCNP Visual Editor

Unstructured Mesh with MCNP–Tutorial

Reactor Physics Design, Validation, and Operating Experience—I

Analysis of a Generic Small Modular Integral Pressurized Water Reactor: Burnable Absorber Rod Materials

Evans Kitcher, Sunil Chirayath (Texas A&M)

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

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

A Systematic Core Design Optimization of the Purdue Novel Modular Reactor (NMR-50)

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

Neutronic Modeling of Additively Manufactured HFIR Control Elements

J. R. Burns (Georgia Tech, ORNL), D. Chandler (ORNL), Bojan Petrovic (Georgia Tech), Kurt A. Terrani (ORNL)

Development of In-Core Detector Devices for Steady-State and Transient Measurements

Jan Vermaak, Marvin Adams (Texas A&M)

Reactor Physics Design, Validation, and Operating Experience—II

Extreme Performance Multibatch Research Reactor Based on Simple Plate Fuel

Paolo Venneri, Yonghee Kim (KAIST)

Criticality Benchmarks for Validation of SERPENT as an ATR-LEU Conversion Reactor Physics Tool

Jorge Navarro, Mark D. DeHart (INL)

Mapping of Biases and Uncertainties from Fresh Fuel Experiments to Depleted Fuel

Dongli Huang, Hany S. Abdel-Khalik (Purdue Univ)

Requalification and Experimental Validation of the Epithermal Neutron Beam Facility for Radiotherapy Research at Washington State University

David W. Nigg (INL), Kaitlyn R. Restis, Sara M. Dickens, C. Corey Hines, Mathew D. King, Alexandra Bartkoski, Donald E. Wall (Washington State Univ)

Development of Hodoscope-Reactor Core Model for TREAT Transient Testing

Logan Michael Scott, Samuel E. Bays (INL)

Compact Reactors for Terrestrial and Space Applications

Legacy Potassium Worth Measurement, and Its Associated Calculational Bias, in a Mockup of UO₂, Beryllium-Reflected Space Reactor

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

Advances in Fast Reactor Designs and Concepts

An Optimized Core Design of Passively Safe Liquid Fuel Reactor SLFFR for TRU Burning

T. Jing, G. Yang, Y. S. Jung, W. S. Yang (Purdue Univ)

Physics Study of Sodium Cooled Ultra-Long-Life Core using New Driver-Blanket Burnup Strategy

HaeRi Hyun, Ser Gi Hong, Wusueng You (Kyung Hee Univ)

Design of a Low-Enriched Uranium Fast Reactor for Maximum Fuel Resource Utilization

Ching-Sheng Lin, Jacob S. Hader, Tongkyu Park, Won Sik Yang (Purdue Univ)

The Potential Impact of FFTF Passive Safety Tests on the Design of New LMRs

D. W. Wootan (PNNL)

A Preliminary Study on the Self-Sustainability of a Sodium-cooled Breed-and-Burn Fast Reactor (B&BR)

Donny Hartanto, Yonghee Kim (KAIST)

Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D

Jonathan B. Scherr, Pavel V. Tsvetkov (Texas A&M)

Compact Sodium-cooled Fast Reactor with Thorium Breed and Burn Blanket

Guanheng Zhang, Massimiliano Fratoni, Jasmina Vujic, Ehud Greenspan (Univ of California, Berkeley)

Reactor Analysis Methods—I

Is 3-D Resonance Self-shielding Calculation Necessary for the Direct Transport Method in LWR Analysis?

Yuxuan Liu, William R. Martin (Univ of Michigan)

Analysis of LEU Pincell and Assembly Benchmark using VISWAM Code

Arvind K. Mathur, Suneet Singh (Indian Institute of Technology), Suhail Ahmad Khan, V. Jagannathan (BARC), L. Thilagam (Safety Research Institute)

GeN-Foam: A Novel Multi-Physics Solver for Reactor Analysis – Status and Ongoing Developments

Carlo Fiorina (EPFL), Konstantin Mikityuk (Paul Scherrer Institut), Andreas Pautz (EPFL, Paul Scherrer Institut)

Impact of 3D Modeling and Homogenization of Control Rods on Reactivity in CFV-type SFR Cores

Mikael Andersson (Chalmers Univ, CEA), David Blanchet (CEA), Henrik Nylén (Chalmers Univ), Robert Jacqmin (CEA)

Reactor Analysis Methods—II

Uncertainty Estimation of Analysis Model using the Data Assimilation Method

Kuniharu Kinoshita, Tomohiro Endo, Akio Yamamoto (Nagoya Univ)

ATR MCNP Model Axial Xenon Oscillation-Free Validation

G. S. Chang, J. W. Nielson, John D. Bess (INL)

3D Power Shape Matching Method for Power Adaptation in the Online Core Monitoring System

Joo Il Yoon, Hae Chan Lee, Young Ho Park (KEPCO)

Fission Probability Density Functions for Kinetic Analysis in Weakly Coupled Fuel Debris

Toru Obara, Delgersaikhan Tuya, Hiroki Takezawa (Tokyo Inst of Technol)

Underestimation of Statistical Uncertainty of Monte Carlo Method with Non-Analog of Fission Source Sampling

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

Kinetic Analysis of Weakly Coupled Fuel Debris by Integral Kinetic Model

Delgersaikhan Tuya, Toru Obara, Hiroki Takezawa (Tokyo Inst Technol)

Application of Partially-Converged Solution of Assembly Calculation for Core Sensitivity Analysis based on Reduced Order Modeling

Ryota Katano, Akio Yamamoto, Tomohiro Endo (Nagoya Univ)

Reactor Analysis Methods—III

A Modified Piecewise Constant Approximation for Solution to the Point Kinetics Equations

Barry Ganapol, P. Picca (Univ of Arizona)

Reactor Power Distribution Calculation in Research Reactors Using MCNP

Zeyun Wu (NIST, Univ of Maryland), Robert E. Williams (NIST)

Position-Dependent Delayed-Neutron Fractions for IQS Calculations in the Diffusion Code DONJON and Application to PT-SCWR Reactors

Qingjie Liu, Eleodor Nichita (Univ of Ontario Inst Technol)

Comparative Analysis of SBLOCA With and Without Fuel Behaviour Models

Amjad Nawaz, Hidekazu Yoshikawa, Ming Yang (Harbin Engineering Univ), Anwar Hussain (Pakistan Inst of Engineering and Applied Sciences)

Iterative Shannon Entropy Approach for Efficient Monte Carlo Source Convergence Diagnostics

Bojan Petrovic, David Koch (Georgia Tech)

Multi-Physics Simulation of TREAT Kinetics using MAMMOTH

Mark DeHart, Frederick Gleicher, Javier Ortensi (INL), Anthony Alberti, Todd Palmer (Oregon State Univ)

Simulation Tools and Approaches for the Compliance with Performance-based ECCS Cladding Acceptance Criteria (10 CFR 50.46C)

A. Zoino (Sapienza Univ of Rome), A. Alfonsi, C. Rabiti (INL), F. Giannetti, G. Caruso (Sapienza Univ of Rome)

Reactor Physics: General—I

Location Specific Dancoff Factors for Nonuniform PWR Lattices

Steven A. Thompson (Dominion Generation)

Radial Power Profile of Gadolinia Fuel Pins

Steven A. Thompson (Dominion Generation)

Implementation of Unionized Energy Grid and Woodcock Tracking in RMC Code

Shichang Liu, Jin-gang Liang, Kan Wang (Tsinghua Univ)

Theoretical Expression of Area Ratio Method Using Detected-Neutron Multiplication Factor

Tomohiro Endo, Akio Yamamoto (Nagoya Univ)

Assessment of the Validation Domain of Reduced Order Modeling

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

Reactor Physics: General—II

Sensitivity and Uncertainty Analysis of Modeled Pu and Cs Isotope Ratios in a Test Pressurized Water Reactor

Andrew Conant, Anna Erickson (Georgia Tech), Martin Robel (LLNL)

Power Density Uncertainties in 2D Full Core Serpent Simulations

Kyle M. Ramey, Bojan Petrovic (Georgia Tech)

2D Serpent Model for I²S-LWR Radial Reflector Studies

Kyle M. Ramey, Bojan Petrovic (Georgia Tech)

Uncertainty Analysis of Th-Fueled Sodium-cooled Fast Reactor

Gerardo Aliberti, Florent Heidet, Nicolas E. Stauff, Taek K. Kim, Temitope A. Taiwo (ANL)

The Optimization of Subgroup Levels with the Simulated Annealing Method

Hansol Park, Han Gyu Joo (Seoul National Univ)

Generation of KARMA Library with MCNP-GenP Code System and Its Verification

Jeong-yeup Lee, Hae-chan Lee, Chan-oh Park, Hae-seuk Woo (KEPCO)

Numerical Application of the Sjöstrand Method without the Pulses Superimposition Methodology

A. Talamo, Y. Gohar (ANL)

Reactor Physics: General—III

Solution of the Hot Zero Power BEAVRS Using a Pin-Cell Homogenized Model

Javier Ortensi (INL), Matthew Ellis (MIT), Yaqi Wang (INL), Hans R. Hammer, Jaron P. Senecal (RPI), Frederick N. Gleicher, Sebastian Schunert, Mark D. DeHart (INL), Kord Smith (MIT), R. Martineau (INL)

In Phase Xenon Oscillations- A Non Linear Study

Abhishek Chakraborty (Nuclear Power Corp of India LTD), Suneet Singh (Nuclear Inst of Technol Bombay), M.P.S.Fernando (Nuclear Power Corp of India LTD)

Automated MCDancoff Factor Generation for Liquid Salt Cooled Reactor Parametric Studies

L. Michael Huang, Bojan Petrovic (Georgia Tech)

A Hypothetical Molten Uranium Fueled Mixed Spectrum Nuclear Reactor

Neal L. Mann (Consultant)

A Neutronics Study on Annular Fuel Filled with Burnable Absorber

Mohd-Syukri Yahya, Donny Hartanto, Yonghee Kim (KAIST)

Burnable Poison Reactivity Control for the Advanced High Temperature Reactor

Cole Gentry, G. Ivan Maldonado, Ondrej Chvala (Univ of Tennessee, Knoxville), Bojan Petrovic (Georgia Tech)

Reactor Physics: General—IV

Development of a MCNP6 - ANSYS FLUENT Multiphysics Coupling Capability

William Gurecky, Erich Schneider (Univ of Texas at Austin)

Proposal of Accelerator-Driven System for Neutron Source in Kyoto University Research Reactor Institute

Cheol Ho Pyeon, Tadafumi Sano, Yasuyuki Fujihara, Hiroshi Yashima, Yasushi Saito, Yuji Kawabata (Kyoto Univ)

Application of the Karhunen-Loève Transform to the C5G7 Benchmark in the Response Matrix Method

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

Application of Data Assimilation based on Bayesian Theory to Subcriticality Measurements using Area Ratio Method

Kensuke Maeno, Tomohiro Endo, Akio Yamamoto (Nagoya Univ)

Impacts of Burn-up Measurement Errors on Discharge Burn-up of PB-HTR

Xia Bing, Li Fu (Tsinghua Univ)

Assessment of Power and History Effects on Thorium-Based Fuels in Pressure-Tube Heavy Water Reactors

Blair P. Bromley (Canada Nuclear Laboratories), P. Sambavalingam (Univ of Ontario), G.W.R. Edwards (Canada Nuclear Laboratories)

Nuclear Data Experiments, Evaluations, and Benchmarks

The New OECD-NEA Nuclear Data and Sensitivity Tool (NDaST)

J. Dyrda, I. Hill, M. Bossant, J. Gulliford & N. Soppera (OECD NEA)

Assessing Accuracy of Independent Fission Yield of ²³⁵U by Aggregate Decay Properties

Satoshi Chiba (Tokyo Inst of Technol, National Astronomical Observatory of Japan), Ryohei Shioya, Chikako Ishizuka (Tokyo Inst of Technol)

Verification and Validation of New Unmodified SCALE PWR Lattice Templates

Nathan T. Shoman, Steven E. Skutnik (Univ of Tennessee, Knoxville)

U Determination using an In-Beam Delayed Neutron Counting Technique at the NRU Reactor

M.T. Andrews (LANL), G. Bentoumi (Canadian Nuclear Laboratories), E.C. Corcoran (Royal Military College of Canada), I. Dimayuga (Canadian Nuclear Laboratories), D.G. Kelly (Royal Military College of Canada), L. Li, B. Sur, R.B. Rogge (Canadian Nuclear Laboratories)

Physics in Fusion and Sub-Critical Systems

Neutronic Flux Analysis In Subcritical Systems Using The R/S And DFA Methods

Edson Henrice Jr. (PEN/COPPE), Daniel A. P. Palma (CNEN), Alessandro C. Gonçalves (PEN/COPPE),  Amir Z. Mesquita (CDTN)

Monte Carlo Simulation Software SuperMC 2.2 for Fusion and Fission Applications

Jing Song, Yican Wu, FDS Team (Chinese Academy of Sciences)

Conceptual Design of Fusion Blanket Test Module for Tritium Breeding

SeongHee Hong, YunSeo Park, Myung Hyun Kim (Kyung Hee Univ)

Rapid Visualized Neutronics Modeling of Lead-based Research Reactor for ADS

Quan Gan, Shengpeng Yu, Bin Wu, Jing Song, Mengyun Cheng Feng Wang, FDS Team (Chinese Academy of Sciences)

Helicon Plasma Injection into an Inertial Electrostatic Confinement Fusion Device

G. Chen, G. H. Miley (Univ of Illinois at Urbana-Champaign)

Transient Analysis of an ADS Burner in Industrial Scale

Liangzhi Cao, Mingtao He, Youqi Zheng, Hongchun Wu (Xi’an Jiaotong Univ)

Robotics and Remote Systems: General

Automated Industrial Manufacturing in Hazardous Glovebox Environments

Clinton Peterson, Mitch Pryor (NNL), Brian O’Neil (LANL)

 Unmanned Aerial Vehicle Technology for the Nuclear Industry

Michael Johnson, Khamel Abdulai (Excelsior College)

Two-Phase Flow

Local Measurement of Adiabatic Two-Phase Flow in an Annulus under Low-Frequency Vibration

Guanyi Wang (Purdue Univ), Xiu Xiao (Purdue Univ, Tsinghua Univ), Qingzi Zhu, Xiaohong Yang (Purdue Univ), Shao-Wen Chen (Purdue Univ, National Tsing Hua Univ), Mamoru Ishii (Purdue Univ)

Experiments in Horizontal Bubbly-to-Plug and Bubbly-to-Slug Transition in Two-Phase Flow

R. Kong, S. Kim (Penn State)

Identification of Bubble Interaction Mechanisms Using Image Processing Technique

Yucheng Fu, Yang Liu (Virginia Tech)

Multidimensional Modeling of Two-Phase Flow in PWRs with Mixing Vane Spacer Grids

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

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

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

Prediction of Base Film Thickness of Vertical Upward Co-current Annular Flow in Pipes

Peng Ju (Purdue Univ), Yang Liu (Virginia Tech), Mamoru Ishii (Purdue Univ)

Sensitivity Study of X-Ray Line Detector for Void Fraction Measurement

Kyle Song, Yang Liu (Virginia Tech)

Modeling of Interfacial Forces for Bubbly Flows in Subcooled Boiling Conditions

D. R. Shaver, M. Z. Podowski (RPI)

Thermal Hydraulics Education–Panel

Thermal Hydraulics: General—I

Simulation of BWR Mark I Station Black-Out Accident Using GOTHIC: An Initial Demonstration

Han Bao (NCSU), Haihua Zhao, Hongbin Zhang, Ling Zou, Ronaldo H Szilard (INL), Nam Dinh (NCSU)

A Heat Transport Analytical Benchmark Problem for Sensitivity Analysis, Uncertainty Quantification and Predictive Modeling: I: Verification of the FLUENT Adjoint Solver

Dan G. Cacuci, Ruixian Fang, Madalina C. Badea, Milica Ilic (Univ of South Carolina)

A Heat Transport Analytical Benchmark Problem for Sensitivity Analysis, Uncertainty Quantification, and Predictive Modeling: II: Best Estimate Predictions with Reduceed Uncertainties

Madalina C. Badea, Dan G. Cacuci (Univ of South Carolina)

A Heat Transport Analytical Benchmark Problem for Sensitivity and Uncertainty Analysis. III: Using the 2nd-ASAM to Quantify the Impact of Second-Order Sensitivities and Uncertainties

Dan G. Cacuci (Univ of South Carolina)

Design of an Advanced Intermediate Heat Exchanger for Supercritical CO2 Brayton Cycle

X. Zhang, X. Sun, R.N. Christensen (Ohio State)

Preliminary Safety Analyses on a Conceptual LEU Fueled Research Reactor at NIST

Zeyun Wu (NIST, Univ of Maryland), Robert E. Williams, J. Michael Rowe (NIST)

Development of Core Analysis Model for Evaluating DNBR Power Operating Limit in OASIS

Shane Park, Wi-Soo Jeong, Hae-Chan Lee, Young Ho Park (KEPCO)

Preliminary 2D Analysis of the AHTR Fuel Assembly Removal Transient

Pietro Avigni, Bojan Petrovic (Georgia Tech)

Thermal Hydraulics: General—II

Sensitivity Study of 1F1 Type Accident by MELCOR Code

Kenta Saito, Akifumi Yamaji (Waseda Univ)

Developments of a Modular Graphical Tool for RELAP5

Zhu Haishan, Peng Minjun, Tian Zhaofei (Harbin Engineering Univ)

The SBO Analysis With URG Procedure For LUNGMEN ABWR Using TRACE/FRAPTRAN Codes

Y.T. Li, S. W. Chen, J. R. Wang, C. Shih (National Tsing-Hua Univ)

The Study of Cesium Iodide Transportation in Containment of a Generation III+ Boiling Water Reactor under Bypass Condition

Pinsurang Kittiwarapon, Somboon Rassame (Chulalongkorn Univ), Kampanart Silva (Thailand Inst of Nuclear Technol)

Experimental Thermal Hydraulics—I

Low Pressure Contact Resistance Characterization for HTTF Graphite Interfaces

M. A. Hertel, B. G. Woods, G. C. Blake (Oregon State Univ)

Particle Image Velocimetry on a Single Buoyant Plume of the Very High Temperature Gas-Cooled Reactor

Jae-Hyung Park, Anas Alwafi, Saya Lee, Yassin A. Hassan, N. K. Anand (Texas A&M)

Ultrasonic Inspection Technique for Fuel Debris Combining Ultrasonic Velocity Profiler and Aperture Synthesis Methods

Takuya Kawachi, Tomonori Ihara, Hiroshige Kikura (Tokyo Inst of Technol)

PWR Fuel Bundle Response to Earthquake Motions in Still Water

Noah A. Weichselbaum, S. Hussain, M. Rahimi Abkenar, M. T. Manzari, P. M. Bardet (George Washington Univ)

Three dimensional phase averaged velocity in PWR Fuel Bundles under external forcing

Noah A. Weichselbaum, S. Hussain, M. Rahimi Abkenar, M. T. Manzari, P. M. Bardet (George Washington Univ)

Integral Effect test on Operational Performance of the PAFS for a SGTR Accident

Yusun Park, Byoung-Uhn Bae, Seok Kim, Kyoung-Ho Kang (KAERI)

Development of Two-color/Two-dye Planar Laser Induced Fluorescence (PLIF) Using a Single Color Camera

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

Two-Phase Swirling Flow in a Gas-Liquid Separator

Hayato Funahashi, Kosuke Hayashi, Shigeo Hosokawa, Akio Tomiyama (Kobe Univ)

Experimental Thermal Hydraulics—II

Molecular Tagging Velocimetry Development for In-Situ Measurement in High-Temperature Test Facility

Matthieu A. Andre, Philippe M. Bardet (George Washington Univ), Ross A. Burns (National Inst of Aerospace), Paul M. Danehy (NASA)

Experimental Investigation of Approach Velocity Effect on the Fibrous Debris  Penetration through a Containment Sump Strainer for Generic Safety Issue 191

Sero Yang, Vasileios Kyriakopoulos, Saya Lee, Rodolfo Vaghetto, Yassin A. Hassan (Texas A&M Univ)

An Experimental Study on Injection Performance of Core Makeup Tank for the SMART Design

Hyun-Sik Park, Hwang Bae, Sung-Uk Ryu, Woo-Shik Kim, Sung-Jae Yi (KAERI)

Quasi-Steady State Analysis of the Global Flow Behavior of a Reactor Cavity Cooling System (RCCS) using Water

Mike Gorman, Yassin A. Hassan (Texas A&M)

Water Vapor Concentration Measurement with TDLAS during VHTR Steam Ingress

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

Study of the Critical Heat Flux on Zircaloy Cladding Surfaces in the COSMOS Facilities

A. Miassoedov, C. Haas, S. Gabriel, G. Albrecht (KIT)

Experimental Investigation on Single Phase Mixing Rate at Laminar and Turbulent Flow Condition in Simulated Subchannels of a Natural Circulation Pressure Tube Type BWR

M. P. Sharma (Homi Bhabha National Inst), A. K. Nayak, R. Rajalakshmi (BARC)

Young Professional Thermal Hydraulics Research Competition

Measurements of Boric Acid Concentration in PASTA Experimental Facility

M. Childs, P. Jones, R. Vaghetto, Y.A. Hassan (Texas A&M)

Fluid Structure Interaction Measurements of a PWR Fuel Bundle with Seismic Forcing

Noah Weichselbaum, P. M. Bardet, S. Hussain, M. Rahimi Abkenar, M. Manzari (George Washington Univ)

Sensitivity of Boundary Conditions and Flow Domain for Pressure Drop Estimation for Molten Salts in a Crossflow Tube Bundle

L. B. Carasik (Texas A&M), D. R. Shaver (RPI), Yassin A. Hassan (Texas A&M)

Newton-Krylov Methods in Solving Phase Appearance Problem Due to Phase Change

Ling Zou, Haihua Zhao, Hongbin Zhang (INL)

Computational Fluid Dynamics (CFD) V&V

Separate Effects Characterization of the NSTF to Support Computational Modeling

D. Lisowski, A. Kraus, M. Bucknor, R. Hu (ANL)

CFD Analysis for the PWR Rod Bundle with Split-Type Mixing Vanes

Shin K. Kang, Yassin A. Hassan (Texas A&M)

Interfacial Forces Evaluation on a Single Bubble in Shear Flows Using Interface Tracking Approach

Jinyong Feng, Igor Bolotnov (NCSU)

Interface Tracking Simulation of Boiling Phenomena – Single Bubble Verification

Mengnan Li, Igor A. Bolotnov (NCSU)

Thermal Hydraulic Challenges and Opportunities in the Licensing of Advanced Reactors–Panel

Computational Thermal Hydraulics—I

Applications of the Lattice Boltzmann Method to Nuclear Thermal Hydraulics Problems

Shin K. Kang, Yassin A. Hassan (Texas A&M)

Demonstration of BEPU Analysis of LBLOCA with RELAP5-3D for High Burnup Fuel

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

Benchmarking Results For Small Column Ion Exchange Model

Si Young Lee, William D. King (SRNL)

Spectral Cascade-Transport Model Implementation into Multiphase CFD Code

C.S. Brown (NCSU), D.R. Shaver (RPI), I.A. Bolotnov (NCSU)

Model Establishment and application of Kuosheng Nuclear Power Plant with RELAP5 MOD 3.3 code through the SNAP Interface

H.C. Chang, J.R. Wang, C. Shih (National Tsing-Hua Univ), S.C. Chiang, T.Y. Yu (Taiwan Power Company)

Thermal-Hydraulic Simulation Framework for the NSTF and Preliminary Comparisons with Experimental Data

Adam Kraus, Darius Lisowski, Matthew Bucknor, Rui Hu (ANL)

Natural Convection in a Rough Cavity

M. Yousaf, S. Usman (Missouri Univ Sci Technol)

Computational Thermal Hydraulics—II

Application of Bubble Tracking Capability for Turbulent Two-phase Flow Simulations of a PWR Subchannel

Jan Fang, Igor A. Bolotnov (NCSU)

Multi-Physics Coupling for Optimization of Cyclotron Targetry

Ellen O’Brien, Matthew H. Stokely, Joseph M. Doster, Igor A. Bolotnov (NCSU)

Computational Study of the Safety Injection Tank Performance

Jai Oan Cho, Jeong Ik Lee (KAIST), Yacine Addad (Khalifa Univ), Yohanes Setiawan Nietiadi (KAIST)

Study on Coolant Temperature Distribution of Core Inlet for IP200

Lin Sun, Minjun Peng, Genglei Xia (Harbin Engineering Univ)

Fuel Temperature Prediction of a Prismatic Gas-Cooled Reactor Using Pin-By-Pin Fuel Power

Nam-il Tak, Tae Young Han, Hyun Chul Lee (KAERI)

Nuclear Politics: Perspectives from ANS Congressional Fellows and Nuclear Advocates–Panel

Student Conference Proposal Writing and Planning–Panel

Young Members Group: General

The Nuclear Energy Knowledge and Validation Center

Hans D. Gougar (INL)

The Development of Nuclear Power Plant and Storage Power Plant in China

Hongjuan Ran, Dezhong Wang (Shanghai Jiaotong Univ)

Postdoctoral Experience at a National Laboratory: A Nuclear Engineering Perspective–Panel

Investigating the Thermal Behavior of Lifetime for a DSS Through CFD

Y. S. Tseng (NSTDC), C. H. Chu, Y. H. Ferng (ESS, NTHU), C. K. Shih (NES, NTHU)

Spectral Advanced Radiological Computer System Applications

Sanjoy Mukhopadhyay, Richard J. Maurer, Henry Adams, James Butler, Rica Salcedo (National Security Technologies, LLC)

A Nodal Kinetics Model for a Subcritical Advanced Burner Reactor

A. T. Bopp, W. M. Stacey (Georgia Tech)

Analysis of Electrochemical Impedance Spectra Using Constant Phase Element for SmCl₃ in LiCl-KCl Eutectic

Dalsung Yoon, Supathorn Phongikaroon (VCU), Michael Shaltry (INL)

Development of Multi-Dimensional Core Transient Analysis Code System

Jin-Woo Park, Guen-Tae Park, Min-Ho Park, Seok-Hee Ryu, Kil-Sup Um, Jae-Il Lee (KEPCO)

CUDA-Accelerated Algorithm in 3D Neutron Diffusion Calculation at the VR-1

Ing. Filip Fejt (Czech Tech Univ in Prague)

Parameterization of Macroscopic Cross Section in Burn-up Cycles

Thiago Freitas Belo (Military Institute of Engineering)

A Spectroelectrochemical Study of Samarium Ions in the Molten LiCl-KCl Eutectic

A. R. Lee, H. J. Han, B. K. Kim, B. G. Park (Soonchunhyang Univ)

Firebrick Resistance-Heated Energy Storage: Existing Technology Base

Richard T. Ibekwe, Charles Forsberg (MIT)

Development of a Baseline Assessment of TREAT for Modeling and Analysis Needs

John D. Bess, Mark D. DeHart (INL)

Experimental Uncertainty Analysis for Critical Assemblies of HEU (93.14 wt.%) Metal Annuli with Internal Graphite Cylinder

Liu Ziaobo (Institute of Nuclear Physics and Chemistry), John D. Bess (INL)

Nuclear Forensics Exercises and Development of Training Aids

Sangjun Lee, Seungmin Lee, Hobin Yim, Jaekwang Kim (Korea Inst Nucl Nonproliferation and Control)

Calculating Gamma Heating in the I²S-LWR Radial Steel Reflector

Timothy Flaspoehler, Bojan Petrovic (Georgia Tech)

Evaluation of Heat Treatment for U-bend Steam Generator Tubes

Manuel Umanzor, Gokul Vasudevamurthy (VCU), Mica Baquera (US NRC)

Modeling Small Pebble Bed Reactor Fuel Loading Concepts with PEBBED

Hans D. Gougar, R. Sonat Sen (INL)

Effects of Relative Heights for SMRs’ Performance

Youngjin Kim, Kunwoo Yi, Changkyu Chung (KEPCO)

Design of a Board Type Breed and Burn Reactor Core

Meiyin Zheng, Wenxi Tian, Guanghui Su (Xi’an Jiaotong Univ)

The Remote Compositional Analysis of Molten Salt (KF-LiF-10wt%ZrF₄) by Probe Assisted In-Situ LIBS System

Seunghyun Kim (VCU), Jonghyeon Lee (Chungnam National Univ), Supathorn Phongikaroon (VCU)

First Update on a Real-time Tumor Localization and Guidance Platform for Radiotherapy Using US and MRI

Bryan Bednarz (Univ of Wisconsin, Madison)

BWR Core Degradation: MELCOR Analysis of CORA-33 Experiment

Eugenia Contreras Zamora, Michael L. Corradini (Univ of Wisconsin, Madison)

Development of a Methodology to Assess the On-Line Maintenance Risk

Jaeho Kim, Moosung Jae (Hanyang Univ)