Winter Meeting 2014 / Volume 111

ANS Officers

Meeting Officials, National Program Committee

Full Issue

Opening Plenary: Nuclear: The Foundation of Clean Energy

ANS President’s Special Session

Special Session: Global Seismic Safety Issues After the Fukushima Daiichi Accident: On Identification and Treatment of Uncertainty About Seismic Issues

Accelerator Applications: General

Upper Limits of Accelerator-Driven Systems with Breeder Materials

Sümer Şahin (Atilim Univ), Başar Şarer, Yurdunaz Çelik (Gazi Univ)

Production of a Tritium-Based Betavoltaic Battery Source via Cyclotron Irradiation

E. F. O’Donnell, H. Xiao, T. Liu, M. T. Bernards, P. J. Pinhero (Univ of Missouri, Columbia)

Neutron Capture Cross Section Measurements Using a Lead Slowing-Down Spectromemter

N. Thompson, A. Lewis, E. Blain, A. Daskalakis, Y. Danon (RPI)

High Power From Fixed-Field Rings in the ADS-Reactor Application

F. Méot, N. Brown, M. Haj Tahar, M. Todosow, N. Tsoupas (BNL)

Compact Accelerator-Based Neutron Source for Bulk Residual Stress Measurements

Tye Gribb (Phoenix Nucl Labs), Thad Heltemes (ANL), Ross Radel (Phoenix Nucl Labs)

Aerospace Nuclear Science and Technology: General

A Small Fission Reactor with an Accident-tolerant Control Drum System for Space Application

Hyun Chul Lee, Tae Young Han, Hong Sik Lim (KAERI)

Nuclear Thermal Propulsion with Only Special Nuclear Material of Low Strategic Significance (Category III)

Michael Eades, Thomas Blue (Ohio State Univ), Leroy Hardin (NRC)

Mid-Band Corrosion in Rover/NERVA Fuels: An Acoustic Response to Turbopump Operation and Their Axial Temperature Profile

R. C. O’Brien, P. J. Husemeyer (INL)

Multi-Layer Shielding Analysis for An Evaluation of SPE Radiation

S. I. Sriprisan, S. K. Aghara (Univ of Mass-Lowell)

GEANT4–Tutorial—I

GEANT4–Tutorial—II

Groundwater/Tritium—Radionuclide Releases to the Subsurface from Nuclear Power Plants and U.S. DOE Facilities–Panel

Evolving Aspects of Decommissioning Commercial Power Reactors in the United States–Panel

Industry Perspectives on the Decommissioning of Nuclear Facilities–Panel

Decommissioning and Environmental Sciences: General

Rosebud™ - A Remotely Operated Submersible Excavator

Richard Engel (ASI Group)

Approaches to Decommissioning of Commercial Nuclear Power Plants: Experience Review

Richard Reid, Richard McGrath (EPRI)

From Lab to Floor: Advanced Robotics for Flexible Component Assembly

Brian E. O’Neil (LANL)

A WBS Application for Dismantling of Nuclear Power Plant

Hee Seoung Park, Seung Kook Park, Chan Ho Song, Jei Kwon Moon (KAERI)

ZionSolutions Dry Cask Storage Project/Supporting Fuel Transfer

William J. Szymczak, Frederick N. Williams (ZionSolutions LLC)

Student Design Competition

Undergraduate Category

Method to Enhance Spent Fuel Pool and Dry Cask Storage

Dustin Giltnane, David Gotthold, Seth Langford, Michael Ratliff, Jessica Shewmaker, Cody Wiggins (Univ of Tennessee-Knoxville)

Core Design Analysis of the Molybdenum-99 Pool Reactor (MoPR)

J. Hader, J. Klimes, J. Marshall, F. Odeh, M. Polek, S. Rafferty (Purdue Univ)

Water-Based Neutron Scintillator Detector Design, Construction, and Testing

Andrew Grice, Kam Yu Lee, Jessica Maddocks, Gregory Peacock, Kevin Reeves (Georgia Tech)

Graduate

Load Following Molten Salt Reactor

William Cook, Jinyong Feng, Lloyd Price (TAMU)

U.S. DOE NEUP-Sponsored Student Research

Simulation of Radiation Re-solution in Uranium Carbide

Christopher Matthews, Andrew Klein (Oregon State Univ)

Multi-State Physics Based Aging Assessment of PWR Steam Generator Tubes Rupture in Case of Primary Water Stress Corrosion Cracking

Askin Guler, Tunc Aldemir, Richard Denning (Ohio State Univ)

System for Testing Thermal Shock in Printed Circuit Heat Exchangers

Ian Jentz, Ben Marzouk, Mark Anderson (Univ of Wisconsin-Madison), Xiaodong Sun (Ohio State Univ)

Using Multi-Criteria Decision Analysis (MCDA) and the Analytic Hierarchy Process (AHP) for the Selection of a Nuclear Fuel Cycle in the United States Including Public Perceptions

John Swanson, Ishoc Salaam, Sama Bilbao y León (VCU)

Experimental Design and Flow Visualization for the Upper Plenum of a Scaled VHTR

Kyle L. McVay, Jae Hyung Park, Saya Lee, Yassin A. Hassan, N. K. Anand (TAMU)

Small Modular Reactor Response to Errors in Process Variables and Sensors

Price Collins, Belle R. Upadhyaya (Univ of Tennessee-Knoxville)

Anistropic Azimuthal Power and Temperature Distribution Impact on Hydride Distribution

Christopher Dances, Christopher Piotroski, Michael Mankosa (Penn State Univ)

Design of Dynamically Similar Spacer Grid for Fluid-structure Interaction Studies with Surrogate Fuel Assemblies

Noah A. Wichselbaum, Philippe M. Bardet (George Washington Univ)

Cybersecurity: Protecting Our Digital Assets–Panel

Communicating the Benefits of Nuclear Energy in the Age of the Shale Gale–Panel

Finding Common Ground with New Audiences–Panel

Research by U.S. DOE CASL Students–Panel

The Innovations in Fuel Cycle Research Awards Program—A Student Competition

Crack Initiation Behavior of Neutron Irradiated Model and Commercial Stainless Steels in High Temperature Water

Kale J. Stephenson, Gary S. Was (Univ of Michigan)

Metal-Organic Framework Materials as Nanostructured Sorbents for the Nuclear Fuel Cycle

Carter W. Abney, Michaël Carboni, Kathryn M. L. Taylor-Pashow, Wenbin Lin (Univ of Chicago)

EJ-309 Pulse Shape Discrimination Performance with a High Gamma-Ray-to-Neutron Ratio and Low Threshold

A. C. Kaplan, M. Flaska, A. Enqvist, J. L. Dolan, S. A. Pozzi (Univ of Michigan)

A New On-the-Fly Sampling Method at Thermal Energies for Monte Carlo Codes

Andrew T. Pavlou, Wei Ji (RPI)

Supporting a Thorium-Fueled Reactor Fleet in the U.S. with Domestic By-Product Thorium

Timothy Ault, Steven Krahn, Allen Croff, Raymond Wymer (Vanderbilt Univ)

Permeability Analysis of Cement Sealant for Deep Borehole Repositories

Alex Salazar (Univ of California-Berkeley)

Education, Training, and Workforce Development: General

Reactor Laboratory Modules Available at the UMass-Lowell Research Reactor

John R. White (Univ of Mass-Lowell)

A 3D, Virtual Research Reactor with Interactive Control Room

Yoshinori Satoh (Univ of Illinois U-C, Toshiba Co), Ye Li, Xuefeng Zhu, Rizwan-uddin (Univ of Illinois U-C)

A Simple Point Kinetics Model for Operator Training

Bruce R. Hugo (Energy Northwest, Washington State Univ), Ronald P. Omberg (PNNL)

Educational Training of Handling Naturally Occurring Radioactive Material (NORM) in the Oil and Gas Industry

Shauna G. Landsberger, Graham George (EPDI), Sheldon Landsberger (Univ of Texas at Austin)

Progress in U.S. DOE’s Fuel Cycle Research and Development Program–Panel

Thorium Fuel Cycle—Overview

The Context, Structure, and Objectives of the Thorium Fuel Cycle Technical Track

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

Thorium Fuel Cycle Option Screening and Path Forward in the U.S.

Temitope A. Taiwo, Taek. K. Kim (ANL), Roald A. Wigeland (INL)

OECD NEA Review Activities on the Introduction of Thorium in the Nuclear Fuel Cycle

F. Michel-Sendis, S. Cornet, J. Gulliford (OECD)

Thorium Research Interested in the UK

K. W. Hesketh (UK Natl Nucl Lab)

An Overview of the Thorium Program Plan of the Chinese Academy of Sciences

Hongjie Xu, Zhimin Dai, Xiangzhou Cai (Chinese Academy of Sciences)

Technical Aspects of Thorium Use in Nuclear Reactors

Michael Todosow (BNL)

Overview of the Thor Energy Thorium Fuel Development Program

Saleem S. Drera, Julian F. Kelly, Øystein Asphjell, Klara Insulander Björk (Thor Energy)

Fuel Cycle Options Analysis–Papers/Panel—I

Nuclear Fuel Cycle Options Evaluation and Screening

R. Wigeland (INL), T. Taiwo (ANL), M. Todosow, H. Ludewig (BNL), W. Halsey (LLNL), J. Gehin, R. Jubin (ORNL), J. Buelt (JLB EnvEn Solutions), S. Stockinger (DOE), K. Jenni (Insight Decisions), B. Oakley (Scully Capital)

Value of Utility-Informed Perspectives and the Assessment of Implementation Pathways to Advanced Nuclear Fuel Cycle Objectives

Andrew Sowder (EPRI)

Fuel Cycle Scenarios, Challenges, and Opportunities – A UK Perspective

Fiona Rayment, Tim Tinsley, Robin Taylor, Robert Gregg (UK Natl Nucl Lab)

Panel Discussion

Fuel Cycle Options Analysis—II

Screening and Evaluation Tool for Nuclear Fuel Cycles

Layne Pincock, Brent Dixon (INL)

Analysis of a Three-Stage Fuel Cycle with Heterogenous and Homogenous Thorium-based Fuel in Thermal Reactors and Transmutation of Transuranic Elements in an Accelerator Driven System

Nicholas R. Brown, Michael Todosow (BNL)

Assessment of a Closed Fuel Cycle Using Less Attractive Material in a Small Modular Fast Reactor

N. E. Stauff, T. K. Kim, T. A. Taiwo (ANL), R. A. Wigeland (INL)

Fuel Cycle Options Analysis—III

Evaluation Criteria for Analyses of Nuclear Fuel Cycles

Margaret Flicker, Erich Schneider, Paul Campbell (Univ of Texas at Austin)

Development of Integrated Assessment Model for Nuclear Fuel Cycle Options

Sungyeol Choi, Won Il Ko (KAERI)

Deployment Optimization with the CYCLUS Fuel Cycle Simulator

Robert W. Carlsen, Matthew J. Gidden, Paul P. H. Wilson (Univ of Wisconsin-Madison)

Extensions to the CYCLUS Ecosystem in Support of Market-Driven Transition Capability

Kathryn D. Huff, Massimiliano Fratoni (Univ of California-Berkeley), Harris R. Greenberg (LLNL)

Impacts of Nuclear Material Management Approaches on Fuel Cycle Performance

T. A. Taiwo, T. K. Kim, N. E. Stauff (ANL), R. A. Wigeland (INL)

Fuel Cycle Assessment: Evaluation and Analyses Using ORION for U.S. Fuel Cycle Options

Eva Sunny (ORNL), Robert Gregg (UK Natl Nucl Lab), Tim Ault (Vanderbilt Univ), Jess Gehin, Josh Peterson, Jeff Powers, Andrew Worrall (ORNL)

Thorium Resources, Recovery, Fuels and Fuel Cycles

Environmental Impact of Thorium Recovery from Titanium Mining in North America

Timothy Ault, Steven Krahn, Allen Croff, Raymond Wymer (Vanderbilt Univ)

Thorium Recovery from Rare Earth Element Deposits in the U.S.

Bradley Van Gosen (U.S. Geological Survey), Steven Krahn, Timothy Ault (Vanderbilt Univ)

Separation and Purification of Thorium by Solvent Extraction Processes

Wuping Liao (Chinese Academy of Sciences)

Development of LWR Fuels Utilizing Thorium Dioxide in Conjunction with both Zirconium-Based and SI-C Cladding

Saleem Drera (Thor Energy), Herbert Feinroth (Ceramic Tubular Products LLC), Julian F. Kelly, Klara Insulander Björk (Thor Energy)

Neutronic Design Study of New Small LWR Core Having ThO₂-UO₂and FCM Particle Fuels for TRU Burning

Gonghoon Bae, Ser Gi Hong (Kyung Hee Univ)

Safety Issues of Thorium Utilization in Commercial LWRs

Brian Ade, Andrew Worrall, Jeffrey Powers, Steve Bowman (ORNL)

Thorium Reactors

Innovative Portable Small Nuclear Reactor Using Ceramic Micro-Encapsulated Thorium Fuel

Michael Worrall, Zeev Shayer (Colorado School of Mines)

Heterogeneous Annular Core Concepts for Plutonium-Thorium Fuels in Pressure-Tube Heavy Water Reactors

Blair P. Bromley (AECL)

Preliminary Study of Advanced Sodium-Cooled Burner Reactors with External and Internal Thorium Blankets

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

Thorium Fuelled Resource-Renewable BWR (RBWR) Design Update

Phillip Gorman, Sandra Bogetic, Jia Hou, Jeffrey E. Seifried, Guanheng Zhang, Jasmina Vujic, Ehud Greenspan (Univ of California-Berkeley)

Simulations of a Heavy-Water Reactor Operating on Self-Sufficient Equilibrium Thorium Cycles

Sourena Golesorkhi (Univ of Ontario Inst. of Technology), Blair P. Bromley (AECL), Matthew H. Kaye (Univ of Ontario Inst. of Technology)

Feasibility of Thorium-Hydride Fueled Sodium-Cooled Self-Sustaining Reactors

Guanheng Zhang, Ehud Greenspan (Univ of California-Berkeley)

Burning Weapons Grade Plutonium in Thorium and Uranium with Silicone-Carbide Cladding

Nathan Andrews, Yanin Sukjai, Koroush Shirvan, Ed Pilat, Mujid S. Kazimi (MIT)

Liquid Fuel Molten Salt Reactors for Thorium Utilization

Jess C. Gehin, Jeffrey J. Powers (ORNL)

Factors Affecting Implementation of Industrial-Scale Used Fuel Recycle in the United States–Panel

Storage and Transportation of Used Nuclear Fuel—I

Establishing Technical Basis for Extended Long-Term Storage of Used Fuel

Y. Y. Liu, O.K. Chopra, D. R. Diercks, Z Han, R. R. Fabian (ANL)

Consequence Assessment of Fuel Reconfiguration for Dry Storage and Transportation Packages

J. M. Scaglione, G. Radulescu, K. Robb, W. J. Marshall (ORNL)

Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life

Bret van den Akker, Rob Howard (ORNL)

Integrated Data and Analysis Tool for Used Nuclear Fuel Management

K. Banerjee, J. M. Scaglione, R. A. LeFebvre (ORNL)

Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants

K. W. Cummings (NEI)

Spent Nuclear Fuel Shipment by Air from Hungary to Russia

Ferenc Gajdos, István Vidovszky (Hungarian Academy of Sciences), John Dewes (SRNL)

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Steven J. Maheras, Ralph E. Best, Steven B. Ross, Kenneth A. Buxton (PNLL), Jeffery L. England (SRNL), Paul E. McConnell (SNL)

Storage and Transportation of Used Nuclear Fuel—II

Thermal Modeling Capability Development for As-Loaded Commercial Used Nuclear Fuel Casks

Kevin R. Robb, Remy R. Devoe (ORNL), Thomas E. Michener (PNNL), John M. Scaglione (ORNL)

Current DCSS Thermal Analysis for Extended Storage of Spent Nuclear Fuel

Alexander Velazquez-Lozada, Ghani Zigh, Jorge Solis (NRC)

Spent Fuel Pool K-Effective Sensitivity to Uniform Neutron Absorber Degradation

Amrit Patel (NRC)

Mitigation Potential of Higher Burnup Fuel in Spent Fuel Pools with Uniform Neutron Absorber Degradation

Amrit Patel (NRC)

Dry Storage Cask Shake Table Experiments

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

A Bayesian Approach to Monitoring Spent Fuel Using Cosmic Ray Muons

S. Chatzidakis, M. Alamaniotis, L. H. Tsoukalas (Purdue Univ)

Update on Status on Policy Issues in Waste Management–Panel

Thorium Fuel Reprocessing and Waste Management

Impact of Thorium Fuel Processing on Waste Generation Rates

R. T. Jubin (ORNL), T. Taiwo (ANL), R. Wigeland (INL)

Differences in Thorium and Uranium Fuel Reprocessing

Raymond Wymer, Allen Croff, Timothy Ault, Bethany Smith, Steven Krahn (Vanderbilt Univ)

An Assessment of the Attractiveness of Material Associated with Thorium Fuel Cycles

Charles G. Bathke, Holly R. Trellue (LANL), Bartley B. Ebbinghaus (LLNL), Brian A. Collins, Andrew W. Prichard, Brian W. Smith (PNNL)

Safeguards Considerations for Thorium Fuel Cycles and Associated Nondestructive Assay Challenges

L.G. Worrall, A. Worrall, S. Croft, R.D. McElroy, A.M. Krichinsky, C.A. Pickett, J.L. White-Horton, J.M. Whitaker (ORNL)

Comparative Assessment of Thorium Fuel Cycle Radiotoxicity

Allen G. Croff, Steven L. Krahn (Vanderbilt Univ)

Processing of Graphite Based Nuclear Fuels: A Review

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

Thorium Fuel Cycle Pilot Experiences at Oak Ridge National Laboratory

E. D. Collins, B. D. Patton, A. M. Krichinsky, D. F. Williams (ORNL)

Fuel Cycle and Waste Management: General—I

Why Reconsider a Molten Salt Reactor?

Steven Krahn (Vanderbilt Univ), Charles Forsberg (MIT), Bethany Smith, Timothy Ault (Vanderbilt Univ), Andrew Sowder (EPRI), Nick Irvin (Southern Company)

Reducing the Molten Salt Reactor (MSR) Accident Source Term

Charles Forsberg (MIT)

Burnable Absorber Designs for a Conceptual Boron-Free SMR

Do Ik Change (KEPCO), Hyeong-Heon Kim (KEPCON E&C), Kibong Seong, Jin sun Kim (KEPCO)

Evaluation of the Reactivity Feedback at Hot Full Power Conditions for Sustainable PWR MOX Fuel Cycle

Alexey I. Soldatov, Taylor N. Coddington, Michael A. Perlin, Andrew C. Klein, Todd S. Palmer (Oregon State Univ)

Estimating Worker Collective Doses from a Revised Approach to Managing Commercial Used Nuclear Fuel

Bethany Smith, Steven Krahn, Allen Croff (Vanderbilt Univ), Andrew Sowder (EPRI)

Fuel Cycle Transition Analysis Under Uncertainty

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

Fuel Cycle and Waste Management: General—II

Development of ITER Large Metallic Radioactive Waste Treatment Process

Je Keun Chon (ITER), Hugh Allen (DBD Limited), Byung-Chan Na (ITER)

Separation of SrCl₂ and CsCl from Ternary SrCl₂-LiCl-KCl and Quaternary SrCl₂-CsCl-LiCl-KCl Molten Salts via Melt Crystallization

Ammon N. Williams (VCU), Michael Pack (Univ of Idaho), Supathorn Phongikaroon (VCU)

Characterization of Pentavalent and Hexavalent Americium in Nitric acid using X-ray Absorption Fine Structure Spectroscopy and First-Principles Modeling

C. L. Riddle (INL), K. Czerwinski, E. Kim (Univ of Nevada, Las Vegas), P. D. Paviet (DOE), P. F. Weck (SNL), F. Poineau (Univ of Nevada, Las Vegas), S. Conradson (LANL)

On-Line Spectroscopic Monitoring of a Weak-Acid Based Separation Scheme: pH Measurement Variability and Accuracy

Amanda Casella, Laura Hylden, Amanda Crawford, Forrest Heller, Navindra Gunawardena, Sam Bryan (PNNL)

Modeling Accumulation of Thermally Fissile Material from Waste Canister Array

Alex Salazar, Joonhong Ahn (Univ of California-Berkeley)

Promising Thorium Fuel Cycles, Technology Gaps, and Identification of Data Needs to Support Them–Panel

U.S. Department of Energy Light Water Reactor Sustainability Program

On Developing a Mechanistic Model and Supporting Database to Predict High Fluence-Low Flux Extended Life RPV Embrittlement: Status, Challenges and Opportunities

Peter B. Wells, Nathan Almirall, Takuya Yamamoto, G. Robert Odette (Univ of California, Santa Barbara)

CALPHAD and Cluster Dynamics Modeling of Ni-Mn-Si Precipitate Stability and Kinetics in Reactor Pressure Vessel Steels

Dane Morgan, Huibin Ke, Wei Xiong, Leland Barnard (Univ of Wisconsin-Madison), Peter Wells, G. Robert Odette (Univ of California, Santa Barbara)

Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants using Non-destructive Evaluation

Kevin L. Simmons, Pradeep Ramuhalli, Allan Pardini, Matthew Prowant, Leonard S. Fifield, Jonathan Tedeschi, A. Mark Jones, Matt P. Westman (PNNL)

Comparison of a Traditional Probabilistic Risk Assessment Approach with Advanced Safety Analysis

Diego Mandelli, Zhegang Ma, Curtis Smith (INL)

Status Update on RELAP-7 – A Next Generation Reactor System Analysis Code

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

Implementation of an Advanced Outage Control Center

Shawn St. Germain (INL)

Human Factors, Instrumentation, and Controls—Instrumentation and Controls: General

Reactor Power Reconstruction from External Core Distributed Measurement

Charles Stratton, Pavel Tsvetkov (TAMU)

Development of Digital-device-based Work Verification System for Cooperation in Nuclear Power Plants (NPPs)

Seung Min Lee (KAIST), Hyun Chul Lee (KAERI), Poong Hyun Seong (KAIST)

Ultrasonic Waveguide Transducer for Under-Sodium Defect Detection and Component Recognition

H.-T. Chien, W. P. Lawrence, D. Engel, S.-H. Sheen, C. Grandy (ANL)

Digital Dynamic Compensation Methods of Vanadium Self Powered Neutron Detector

Xingjie Peng (Tsinghua Univ, Nucl Power Inst. of China), Qing Li (Nucl Power Inst. of China), Kan Wang (Tsinghua Univ)

Human Factors, Instrumentation, and Controls Division—Human Factors: General

Evaluation of Safety Culture Indicators for Korean NPPs

Jungwhan Park, Jonghyun Kim (KEPCO Intl Nucl Grad School)

Identification of Human-induced Initiating Event in the Low and Shutdown Operation by using CESA Method

Yongchan Kim, Jonghyun Kim (KEPCO Intl Nucl Grad School)

Design of Task Support Display for Emergency Operating Procedures using Ecological Interface Design

Munwon Choi, Jonghyun Kim (KEPCO Intl Nucl Grad School)

Analysis of Inspection Findings in Terms of Safety Culture Components in Korea

Ji Tae Kim, Young Sung Choi (KINS)

Elimination of Bias in NPP Control Room Simulator Experiments

Rachel Benish Shirley, Carol Smidts, Atul Gupta, Nan Wang (Ohio State Univ)

Nuclear Plant Instrumentation and Control and Human-Machine Interface Technologies 2015—Preview Session

Advancements in Imagining, Nuclear Instrumentation, and Measurement Technologies

A Novel Approach to Automatic Detection of Oral Lesions From CT Images

Shaikat Galib, Fahima Islam, Hyoung Koo Lee (Missouri Univ of Science and Technology)

X-ray Digital Industrial Radiography (DIR) and Particle Tracking Velocimetry (PTV) for Local Liquid Velocity (VLL) Measurement in Trickle Bed Reactors (TBRs)

Hyoung Koo Lee, Khairul Anuar Mohd Salleh, Muthanna H. Al-Dahhan (Missouri Univ of Science and Technology)

Assessment of Nuclear Fuels using Radiographic Thickness Measurement Method

Muhammad Abir, Fahima Islam (Missouri Univ of Science and Technology), Hyoung Koo Lee (Missouri Univ of Science and Technology), Daniel Wachs (INL)

Sparse Sampling Tomographic Reconstruction of Radioactive Fuel Assembly

Muhammad Abir, Fahima Islam (Missouri Univ of Science and Technology), Daniel Wachs (INL), Hyoung Koo Lee (Missouri Univ of Science and Technology)

Deterministic Simulation of Neutron Radiography and Tomography

Rajarshi Pal Chowdhury, Xin Liu (Missouri Univ of Science and Technology)

Insufficient CT Data Reconstruction Based on MLEM- DTV Method

Fahima Islam, Muhammad Abir, Hyoung Koo Lee (Missouri Univ of Science and Technology)

Improving Nuclear Detection: Hodoscope Orthogonal Correlation

Alexander DeVolpi (Nuclear Applications Company)

Isotopes and Radiation: General

Radioxenon Availability for Transport after Fission

S. R. Bielgalski (Univ of Texas at Austin)

A Comparison of the Effects of the Hydroforming and Draw-Plug Assembly Methods on the Thermal-Stresses in an Annular Target with an LEU-Foil and Electroplated Nickel Recoil Barrier

S.G. Govindarajan, G. L. Solbrekken (Univ of Missouri)

Experimental Verification of a Combined Porosity and C/O Logging Tool

Walid A. Metwally (Univ of Sharjah), Qiong Zhang, Feyzi Inanc (Baker Hughes)

Nuclear Measurement of Water Level and Fuel Concentration for Spent-fuel Pools and Reactors

Alexander DeVolpi (Nuclear Applications Company)

Progress on a Petawatt Laser Driven Intense Pulsed Neutron Source

George H. Miley (Univ of Illinois at Urbana-Champaign)

An Evaluation of Compton Suppression NAA in the Determination of Arsenic in Drinking Water in Surfside, Texas

Shauna G. Landsberger, G. George (Enviroklean Product Development Inc.), Sheldon Landsberger, Gleb Kuzmin (Univ of Texas at Austin)

In Situ Determination of Radionuclides in the Oil and Gas Fields

Sheldon Landsberger, Jacob Morton (Univ of Texas at Austin), Shauna G. Landsberger, G. George (Enviroklean Product Development Inc.), Michael Moyamezi, Brad Hurst (Bridgeport Instruments LLC)

Quality Assurance for Gamma-Gamma Coincidence in a Two Source Complex Spectrum

Michael Yoho, Sheldon Landsberger (Univ of Texas at Austin)

⁹³Nb Thermal Neutron Capture Cross-section from Prompt Gamma-Ray Intensities

Danyal Turkoglu (Ohio State Univ), Shamsuzzoha Basunia, Aaron Hurst, Richard Firestone (LBNL), Laszlo Szentmiklosi, Lei Cao (Institut of Isotopes)

Structural Materials and Used Nuclear Fuel Disposition

Microstructure and Mechanical Behavior of Neutron Irradiated Ultrafine Grained Ferritic Steel

Ahmad Alsabbagh, Apu Sarkar (NCSU), Brandon Miller (INL), Jatuporn Burns (CAES), Leah Squires, Douglas Porter, James I. Cole (INL), K. L. Murty (NCSU)

The Used Nuclear Fuel Problem in the USA – Consolidated Storage and Standardized Storage Canisters

Chris Phillips, Ivan Thomas, Steven McNiven (EnergySolutions)

Sensitivity Studies on UNF Cladding Structural Integrity Under NCT Loading

Scott E. Sanborn, Brian J. Koeppel, Ken J. Geelhood, Harold E. Adkins (PNNL)

Polytypic Stabilization of Nanostructured Polymer Derived SiC for Nuclear Applications

Shelly Arreguin (Univ of Washington, PNNL), Rajendra K. Bordia (Clemson Univ), Charles H. Henager, Jr. (PNNL)

Effects of Charged Particle Irradiations in Reactor Pressure Vessel Steels

N. Almirall, P. Wells, T. Yamamoto, G. R. Odette (Univ of California, Santa Barbara)

Low-Temperature Chemical Vapor Deposition of Vanadium Carbide for Mitigating the FCCI

Wei-Tang Lo, Shaosong Huang, Nils Strombom, Yong Yang (Univ of Florida)

Formation of Molten Fluoride Salt Corrosion Resistant Coatings on Nickel-Based Alloys

M. C. Brupbacher, D. Zhang, W. M. Buchta, J. B. Spicer, D. C. Nagle (Johns Hopkins Univ)

Nuclear Fuels

Surface Mapping of Single Crystal ThO₂ with Atomic Force Microscopy

Scott Key, Tony D. Kelly, Alex Li, James Petrosky, John W. McClory (Air Force Inst. of Technology), J. Matthew Mann (Air Force Research Laboratory)

Photoemission Studies of Single Crystal Thorium-Uranium Dioxide Alloys

Glenn Peterson, Tony D. Kelly, James C. Petrosky (Air Force Inst. of Technology), David Turner (Oak Ridge Inst. for Science and Education), John W. McClory (Air Force Inst. of Technology), J. Matthew Mann (Air Force Research Laboratory), Joseph Kolis (Clemson Univ)

The Effect of Fuel Size on the Performance of a U-Mo/Al Dispersion Fuel

Yeon Soo Kim (ANL), J. M. Park (KAERI), B. Ye (ANL)

Preliminary Studies on Volatile Fission Gas Distribution in Minor Actinide-Bearing Metal Fuel

L. Capriotti, S. Bremier (Joint Research Centre), K. Inagaki (CRIEPI), P. Pöml, D. Papaioannou (Joint Research Centre),H. Oha, T. Ogata (CRIEPI), V. V. Rondinella (Joint Research Centre)

Reactor Physics Implications of Advanced SiC-Clad Fuel in PWRs

D. Bloore, K. Shirvan, E. E. Pilat, M. S. Kazimi (MIT)

Transient Experiment Design for Accident Tolerance Fuels

N. E. Woolstenhulme, D. M. Wachs, A. A. Beasley (INL)

Computational Modeling and Corrosion in Nuclear Systems

Simulation of Radiation Re-solution in Uranium Carbide

Christopher Matthews, Andrew Klein (Oregon State Univ)

Anisotropic Azimuthal Power and Temperature Distribution Impact on Hydride Distribution

Christopher Dances, Christopher Piotroski, Michael Mankosa (Penn State Univ)

Redwing: a MOOSE Application for Coupling MPACT and BISON

Michael Rose, Thomas Downar (Univ of Michigan), Frederick N. Gleicher (INL)

An Experimental Study on Bending Fatigue Test with a Krouse-Type Fatigue Specimen

Ahmed S. Haidyrah, Carlos H. Castaño, Joseph W. Newkirk (Missouri Univ of Science and Technology)

Numerical Study of Eddy Current Flaw Detection Techniques in Liquid Metal Reactor

Mohammad R. Quddes, Leonard J. Bond, John R. Bowler (Iowa State Univ)

Monitoring the Structural Change of Graphite under Fast Proton Radiation

H. Xiao, E. F. O’Donnell, P. J. Pinhero (Univ of Missouri, Columbia)

Current Issues in Computational Methods–Roundtable: Reduced Models: Needs and Challenges

Transport Methods: General—I

A High-Order Low-Order Algorithm with Exponentially-Convergent Monte Carlo for k-Eigenvalue problems

S. R. Bolding, Jim E. Morel (TAMU)

Iterative Implicit Monte Carlo

Ben C. Yee (Univ of Michigan), N. A. Gentile (LLNL)

A Modified Simplex Method for Choosing Monte Carlo Scattering Directions

John L. Pevey, Ronald E. Pevey (Univ of Tennessee)

Analysis of Lagged Weight Windows for Implicit Monte Carlo Variance Reduction

Jacob T. Landman, Ryan G. McClarren, Jonathan R. Madsen, Alex R. Long (TAMU)

Woodcock Monte Carlo Transport Through Binary Stochastic Media

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

Benchmark Investigation of a 3D Monte Carlo Levermore-Pomraning Algorithm for Binary Stochastic Media

Patrick S. Brantley (LLNL)

New Hash-based Energy Lookup Algorithm for Monte Carlo Codes

Forrest B. Brown (LANL)

Development of a CAD Based Geometry Model in Serpent 2 Monte Carlo Code

Jaakko Leppänen (VIT Technical Research Centre of Finland)

Transport Methods: General—II

Measuring Angular Discretization Error During TRT Simulations with Energy Collapsed, Single Group Calculations

Alex R. Long, Ryan G. McClarren (TAMU)

Cellwise Block Iteration as a Multigrid Smoother for Discrete-Ordinates Calculations I: Theory

Jeffery D. Densmore, Daniel F. Gill, Justin M. Pounders (Bettis Atomic Power Lab)

Cellwise Block Iteration as a Multigrid Smoother for Discrete-Ordinates Calculations II: Numerical Results

Daniel F. Gill, Jeffery D. Densmore, Justin M. Pounders (Bettis Atomic Power Lab)

Residual Monte Carlo Using Kernel Density Estimators

Brian R. Nease, Jeffrey D. Densmore (Bettis Atomic Power Lab), David L. Millman (ProductionPro)

Computational Methods: General—I

Differential Quadrature Approximation of the Angular Derivative Terms in the Curvilinear-Coordinates S_N Equations

J. S. Warsa (LANL), A. K. Prinja (Univ of New Mexico)

Extension of the Entropy Viscosity Method to the Low-Mach Regime for the Multi-Dimensional Euler Equations

Marc O. Delchini, Jean C. Ragusa, Ray A. Barry (TAMU)

A DFEM Formulation of the Diffusion Equation on Arbitrary Polyhedral Grids

Michael W. Hackemack, Jean C. Ragusa (TAMU)

Validation of Full-Domain Massively Parallel Transport Sweep Algorithms

W. Daryl Hawkins (TAMU), Teresa S. Bailey (LLNL), Marvin A. Adams (TAMU), Peter N. Brown, Adam J. Kunen (LLNL), Michael P. Adams, Timmie Smith, Nancy Amato, Lawrence Rauchwerger (TAMU)

Scalability of Monte Carlo Cross-Section Lookup Algorithms for Large Models

David P. Griesheimer (Bechtel Marine Propulsion Corp)

Using Composite Nuclides to Reduce Cross Section Lookups in Monte Carlo Transport Simulations

David P. Griesheimer, Reza R., Gouw (Bechtel Marine Propulsion Corp)

The Effects of Reference Remapping in WARP, a GPU-Accelerated, Continuous Energy Monte Carlo Neutron Transport Framework

Ryan M. Bergmann, Jasmina L. Vujic (Univ of California-Berkeley)

The Influence in Disregarding the First Approximation of Bethe-Plackzec in the Calculation of Resonance Self-Shielding Factors

Daniel A. P. Palma (CNEN), Alessandro C. Gonçalves, Aquilano S. Martinez (PEN/COPPE), Amir Z. Mesquita (CDTN)

Computational Methods: General—II

A Comparison of Eigensolvers for the SP_N Equations

Steven Hamilton, Tom Evans (ORNL)

Monte Carlo Alpha Iteration Algorithm for a Prompt Neutron Decay Constant Calculation

Hyung Jin Shim, Byoung Kyu Jeon, Soo Min Kang, Chang Hyo Kim (Seoul National Univ)

Heterogeneous Variational Nodal Method with Continuous Cross Section Distribution in Space

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

2-D/1-D Method for Neutron Transport Based on Large-Scale Parallel Computation

Wenbin Wu (Tsinghua Univ, Nuclear Power Inst. of China), Qing Li (Nuclear Power Inst. of China), Kan Wang (Tsinghua Univ)

A Numerical Solution to the Point Kinetic Equations Using Spectral Deferred Correction

Yun Cai (Tsinghua Univ, Nuclear Power Inst. of China), Qing Li (Nuclear Power Inst. of China), Kan Wang (Tsinghua Univ)

Development of Sensitivity Analysis Capability in RMC Code

Yishu Qiu, Kan Wang, Jiankai Yu (Tsinghua Univ)

Uncertainty Quantification and Sensitivity Analysis Methods

Application of the Differential Evolution Adaptive Metropolis (DREAM) Method for Uncertainty Quantification in Inverse Transport Problems

Keith C. Bledsoe (ORNL), Jeffrey A. Favorite (LANL), Jordan P. Lefebvre, Robert A. Lefebvre, Matthew A. Jessee (ORNL)

Sparse-Grid Stochastic Collocation Uncertainty Quantification Convergence for Multigroup Diffusion

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

Mutual Information: A Generalization of Similarity Indices

Paridhi Athe, Hany Abdel-Khalik (NCSU)

Performance Enhancements to the SCALE TSUNAMI-3D Generalized Response Sensitivity Capability

Christopher M. Perfetti, Bradley T. Rearden (ORNL)

On the Importance of Second-Order Response Derivatives for Quantifying Non-Gaussian Features of Computed Model Responses

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

Efficient and Exact Computation of Second-Order Response Sensitivities Using Adjoint Systems: A Paradigm Illustrative Neutron Diffusion Problem

Dan G. Cacuci (Univ of South Carolina)

Further Developments of Inverse Sensitivity/Uncertainty Quantification for High Dimensional-Large Scale Constrained Problems

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

Recent Nuclear Criticality Safety Program Technical Accomplishments

Steady State Neutron and Gamma Measurements of the Godiva Reactor

David P. Hickman, Jennifer G. Burch, Rebecca R. Hudson, Gary W. Slavik, Scott Richardson, John Scorby, Radoslav Radev, Nathaniel Bowden, David P. Heinrichs (LLNL), Joetta Goda, John Bounds, Tom Mclean, Jesson Hutchison, Travis Grove (LANL), Dann C. Ward (SNL), Chris Wilson, Leo Clark (Atomic Weapons Establishment)

ORNL Nuclear Data Evaluation Accomplishment for FY 2013

L. Leal, V. Sobes, M. Pigni, K. Guber, G. Arbanas, D. Wiarda, M. Dunn (ORNL), E. Ivanov, T. Ivanova, E. Letang (Institut de Radioprotection et de Surete Nucleaire)

Nuclear Data Advisory Group Technical Support for the U.S. Nuclear Criticality Safety Program

Michael E. Dunn (ORNL, Safety Program Data Advisory Group)

Godiva IV Startup at National Criticality Experiments Research Center (NCERC): Delayed Critical Through Prompt Critical

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

MCNP Sensitivity/Uncertainty Accomplishments for the Nuclear Criticality Safety Program

Brian C. Kiedrowski, Forrest B. Brown, Jeffrey S. Bull, Albert C. Kahler, D. Kent Parsons (LANL), Matthew A. Gonzales, Anil K. Prinja (Univ of New Mexico)

Management Perspective on Recent Accomplishments and Future Plans for NCERC

Steven D. Clement, William L. Myers (LANL), Jerry N. McKamy (National Nuclear Security Administration), Nichole Ellis (Ellis Engineering LLC)

A Review of Recent R&D Efforts in Sub-Critical Multiplication Measurements and Simulations

Avneet Sood, C. J. Solomon, J. D. Hutchinson, Rian Bahran (LANL)

Data, Analysis, and Operations for Nuclear Criticality Safety—I

List-Mode Simulations of the Subcritical Thor Core Benchmark Sensitivity Experiments

R. Bahran, J. Hutchinson, B. Richard, Avneet Sood (LANL)

Artificial Neural Network Representation of Criticality Excursion Experiment Data

Peter L. Angelo (Y-12 NSC)

Challenges Associated with the Current Demand for UK Criticality Safety Assessors

Ben Webborn (UK Nuclear National Lab)

Nuclear Criticality Evaluation for Vitrified Borosilicate Glass

Glenn A. Christenbury (DOE)

Generation of Thermal Scattering Laws for YH₂ using Ab Initio Methods

Michael L. Zerkle (BAPL)

Safety Related Equipment Implementation and Testing

Joshua M. Marshall (Nuclear Fuel Services, Inc.)

Reevaluation of Room Return Corrections for Two ORCEF HEU-Metal-Cylinder Benchmark Evaluations

John D. Bess (INL)

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

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

Data, Analysis, and Operations for Nuclear Criticality Safety—II

A Computational Approach to the Dissolver Paradox

Alyssa R. Kersting (LANL)

New Critical Experiment Design to Investigate Composite Reflection Effect

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

Nuclear Data Adjustment with SAMMY Based on Integral Experiments

Vladimir Sobes, Luiz Leal, Goran Arbanas (ORNL)

Deciphering the Binning Method Uncertainty in Neutron Multiplicity Measurements

Theresa Cutler, Mark Smith-Nelson, Jesson Hutchinson (LANL)

Assessment of the Need for a Criticality Accident Alarm System

James S. Baker, Robert Newnam, Steve Kessler, David Erickson (Savannah River Nuclear Solutions, LLC)

Fire, Seismic, and other Ex-Process Events and Criticality Safety Risk Acceptance

Shean P. Monahan (SNL), T. P. McLaughlin (Private Consultant), Mark V. Mitchell, D.K. Hayes (LANL)

Mixed Uranium-Plutonium Solution Validation of KENO V. a and KENO-VI in SCALE 6.1.2 and 6.2b3 Using Multigroup and Continuous-Energy ENDF/B-VII.0 Libraries

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

Characterization of the NPOD3 Detectors in MCNP5 and MCNP6

Kimberly Clark, Jesson Hutchinson, C. J. Solomon, Theresa Cutler, Avneet Sood (LANL)

Data, Analysis, and Operations for Nuclear Criticality Safety—III

Determination of Experimental Correlations Using the Sampler Sequence Within SCALE 6.2

W. J. Marshall, B. T. Rearden (ORNL)

Non-Parametric, Extreme-Value Method for Estimating Bias and Bias Uncertainty in Nuclear Criticality Safety

Brian C. Kiedrowski (LANL)

Evaluation of Peak Reactivity Analysis of Boiling-Water Reactor Fuel in Transportation and Storage Casks

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

Nickel-Reflected Plutonium Metal Sphere Subcritical Measurements

Benoit Richard, Jesson Hutchinson, Theresa Cutler, Avneet Sood, Mark Smith-Nelson (LANL)

Validation of k_eff Calculations for Boiling-Water Reactor Fuel at Peak Reactivity in Transportation and Storage Casks

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

Reconstructing Double-differential and Energy-Differential Resonance Cross Sections Using the R-Matrix Limited Formalism in the AMPX Code

Andrew Holcomb (Georgia Tech), Luiz Leal (ORNL), Farzad Rahnema (Georgia Tech), Dorothea Wiarda, Goran Arbanas (ORNL)

Critical and Subcritical Data for the Revision of ANS 8.12 Standard

Debdas Biswas, Dennis Mennerdahl, Christopher Tripp, Scott Revolinski, Kermit Bunde, Jason Huffer, Michael Shea, Dominic D. Winstanley (LLNL)

ANS Standards Forum

The Applications of Systems Engineering in Complex System Safety Analysis for Small Modular Reactors–Panel

Combustible Gas Issues in Nuclear Safety–Panel

Current Topics in Probabilistic Risk Analysis

A Scoping Study of Direct Containment Heating in a Small Modular Reactor

Chih-Wei Chang, Nam Dinh (NCSU)

Comparison of Reliability Criteria Determination Methods in Maintenance Rule

Dong-Wook Jerng, Man Cheol Kim (Chung-Ang Univ)

Conditional Failure Probability Evaluating for NPPs Risk Monitoring

Min Zhang, Zhijian Zhang, Yingfei Ma (Harbin Engineering Univ)

Probabilistic Risk Assessment of Vented Fuel System for Gen. IV Gas Fast Reactor

Renae Lenhof, Andrew Klein (Oregon State Univ)

Methodology for the Incorporation of Passive Component Aging Modeling into the RAVEN/RELAP-7 Environment

Askin Guler (Ohio State Univ), Diego Mandelli, Andrea Alfonsi, Joshua Cogliati, Cristian Rabiti (INL), Tunc Aldemir (Ohio State Univ)

Adaptive Dynamic Event Tree in RAVEN Code

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

U.S. NRC Emergency Preparedness and Incident Response

Modeling and Analysis of Manual Intersection Traffic Control for Application in Evacuation Time Estimate Studies

Scott Parr, Brian Wolshon (LSU)

Advancements in Evacuation Time Estimate Studies Contribute to Improved Protective Action Strategies

Joe Jones (SNL), Randy Sullivan (NRC), Brian Wolshon (LSU)

Modeling Protective Action Strategies Using MACCS

Fotini Walton (SNL)

Hypothetical Risk-Informed and Performance-Based Emergency Preparedness Oversight Regimen

Randy Sullivan (NRC)

Real-Time Computation of Evacuation Time Estimates

Edward Lieberman, Kevin Weinisch (KLD Engineering)

Nuclear Installations Safety: General

Preliminary Probabilistic Safety Assessment for a Korean Research Reactor in the Conceptual Design Stage

Yoon-Hwan Lee, Won-Dea Jung, Su-Hyung Yang (KAERI)

Offshore Floating Nuclear Plant (OFNP) with Spar-Type Platform Design

Jake Jurewicz, Jacopo Buongiorno, Michael Golay, Neil Todreas (MIT)

International Licensing Process and Practices Development - Supporting NPP Licensing as Well as SMRs

Kristiina Söderholm Fortum, Ben Amaba (IBM)

Considerations of Water Injection Timing and Volume in Accident Scenarios Relevant to the Fukushima-Daiichi Nuclear Power Plant

Ahmad Al Rashdan, Pavel Tsvetkov, Karen Vierow (TAMU)

Extending RISMC Capabilities for Real-Time Diagnostics and Prognostics

Diego Mandelli, Curtis Smith (INL)

Preliminary Safety Considerations for the Integral Inherently Safe Light Water Reactor (I2S-LWR)

Eric Welch, Annalisa Manera (Univ of Michigan), Matt Memmott, Paolo Ferroni (Westinghouse), Mingjun Wang, John C. Lee (Univ of Michigan)

Nuclear Installations Safety: Containment Response and Severe Accidents

Filtration of Particulates and Pressure Drop in Fibrous Media in Resolution of GSI-191

Amir Ali, Cody Williams, Edward D. Blandford, Kerry Howe (Univ of New Mexico)

Fiberglass Calcium Leaching Release Rate Characterization in Post LOCA Conditions

Sterling Olson, Kerry Howe, David Pease, Amir Ali, Daniel LaBrier, Edward D. Blandford (Univ of New Mexico)

Resolution of GSI-191: Zinc Chemical Effects During a PWR LOCA Event

David Pease, Kerry Howe, Sterling Olson, Amir Ali, Daniel LaBrier, Edward D. Blandford (Univ of New Mexico)

MOCKA Experiments on MCCI of Metal and Oxide Melt with Siliceous Concrete

A. Miassoedov, J. Foit, T. Cron (Karlsruhe Inst. of Technology)

Consequences of Degraded Containment in a Severe Nuclear Power Plant Accident

Zachary Jankovsky, Christopher Jones, Donald Kalinich (SNL)

Out-Containment Gaseous Iodine Removal Efficiency by Alkaline Spray

Irfan Younus, Man Sung Yim (KAIST)

International Safeguards for UF₆ Containers

The Gulf Nuclear Energy Infrastructure Institute (GNEII): Human Capacity Building for Nuclear Energy for Countries New to Nuclear Energy–Panel

Nuclear Industry’s Role in Nonproliferation Initiatives–Panel

Nuclear Nonproliferation Technical Group: General—I

Comparison of FBR and HFIR Monte-Carlo Simulations with Validation from Gamma Spectroscopy in Support of the NFASP Project

Mathew W. Swinney, Sunil S. Chirayath (TAMU)

Evaluation of Hybrid K-edge Densitometry for Pyroprocessing Material Assay

Matthew T. Cook, Steven E. Skutnik (Univ of Tennessee)

Proliferation Resistance Analysis of Nuclear Fuel Cycle Facilities to Quantify the Importance of Containment, Surveillance and Physical Protection Systems

Royal A. Elmore, Sunil S. Chirayath (TAMU), Stanislav Edreev (Tomsk Polytechnic Univ)

Development of Synthetic Urban Melt Glass for Forensic Analysis

Andrew V. Giminaro, Jerrad P. Auxier, John D. Auxier, Emilie K. Fenske, C. J. Oldham, Matthew T. Cook, Howard L. Hall (Univ of Tennessee)

Application of Bayes’ Theorem for Pulse Shape Discrimination

Mateusz Monterial (Univ of Michigan), Peter Marleau (SNL), Alexis Kaplan, Sara Pozzi (Univ of Michigan)

Evaluations of LEU Conversion Impact on the High Temperature Experiment Performance at the MIT Reactor

Kaichao Sun, David Carpenter, Lin-wen Hu, Thomas Newton Jr. (MIT), Erik Watson (ANL)

Nuclear Nonproliferation Technical Group: General—II

Safeguards and Security Integration for Fuel Cycle Facilities

Benjamin B. Cipiti, M. Jordan Parks, Felicia A. Durán (SNL)

Design of a UIUC Pulsed Neutron Facility for Interrogation of Special Nuclear Materials Using MCNPX

Kyuhak Oh, Brent J. Geuser, Richard J. Kustra (Univ of Illinois Urbana-Champaign)

Effect of Grouping Motivations on State Proliferation Pathways

Meyappan Subbaiah, William S. Charlton, Royal Elmore, Ryan Coogan, David Sweeney (TAMU)

A New Approach for the Characterization of Non-Uniqueness of Used Nuclear Fuel Burnup Signatures

Steven E. Skutnik, David R. Davis (Univ of Tennessee)

Correlated Neutron and Gamma-Ray Emission in MCNP6

Michael E. Rising, Avneet Sood, Patrick Talou, Ionel Stetcu, Toshihiko Kawano (LANL)

Domestic New Nuclear Construction–Panel

Advanced/Gen-IV Reactors

Dispatchable Electricity with Salt-Cooled Reactors, Heat Storage, and Base-load Reactor Operation

Charles Forsberg (MIT)

Tritium Capture in Salt-Cooled Fission and Fusion Reactors

Charles Forsberg, John Stempien, Ron Ballinger (MIT)

Tritium Transport and Corrosion Modeling in the Fluoride Salt-Cooled High-Temperature Reactor

John Stempien, Ron Ballinger, Charles Forsberg (MIT)

The Mitsubishi Small Module High Temperature Gas-cooled Reactor “MHR-50/100is” - Conceptual Design of MHR-100is for a Commercial Plant-

Isao Minatsuki, Sunao Oyama, Hiroki Tsukamoto (Mitsubishi Heavy Industries, Ltd.)

Compact Double-wall Twisted-tube Heat Exchanger for the Fluoride Salt-cooled High-temperature Reactor (FHR) with Implications for In-Service Inspection

Joel Hughes, Edward D. Blandford (Univ of New Mexico)

Summary of Sonoprocessing Applications for Nuclear Technologies and Potential Future Applications

Floren Rubio, Edward D. Blandford (Univ of New Mexico), Leonard J. Bond (Iowa State Univ)

PB-FHR Nuclear Air-Brayton Combined Cycle Natural Gas Price Sensitivity

Daniel Curtis, Charles Forsberg (MIT)

Neutronic Comparison of Liquid Salt Primary Coolants and Novel Assembly Design for a Fluoride Salt Cooled High-Temperature Test Reactor

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

The IAEA Activities in Support of the Near Term Deployment of High Temperature Gas Cooled Reactors

Frederik Reitsma (IAEA)

The Design Analysis of the DC Electromagnetic Pump with the Flowrate of 3 L/min

Geun Hyeong Lee, Hee Reyoung Kim (UNIST)

Transient Analysis of Advanced High Temperature Reactors Using Process Simulation Software

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

New Nuclear Construction Around the World–Panel

Operations and Power: General

ATMEA1&EPR^TM mode T Core Control Innovative Features for High Operating Flexibility

Alain Grossetete (AREVA NP SAS)

The Energy Perspective and Nuclear Role under Global Warming

Hiroshi Ujita, Fengjun Duan (Canon Instit. For Global Studies)

Increasing Biomass Feedstocks for Liquid Fuels Using Salt-Cooled Reactors with Air-Brayton Power Cycles

N. C. Skowronski, Charles Forsberg (MIT)

The Impact of Energy Storage on Nuclear Electricity Economics

Ryan Tipps, Erich Schneider, Christopher van der Hoeven (Univ of Texas at Austin), Charles Forsberg (MIT)

Simplified Market Analysis of Nuclear Energy Storage

Ryan Tipps, Erich Schneider, Christopher van der Hoeven (Univ of Texas at Austin), Charles Forsberg (MIT)

Estimating Evaporation from Spent Fuel Storage Pools Using Tritium

Bruce R. Hugo (WSU), Ronald P. Omberg (PNNL)

Safety Countermeasure of Onagawa NPS after Great East Japan Earthquake

Akiyoshi Obonai, Takao Watanabe, Kazuo Hirata (Tohoku Electric Power Company)

Treatment of Radioactive Contaminants in Off-Gases Using Carbon Supported ETS-10 Nanosorbent

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

An Air-Brayton Combined Cycle Power Conversion System for Small Modular LMFBRs

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

KEPIC Development for Operation of N. P. P in Korea

Geun-Suk Choi, Hoon-Seok Byun, Jong-Hae Kim (KEPIC)

Radiation Protection and Shielding: General

Polymer Nanocomposite Based Neutron Shielding Materials for Spent Nuclear Fuel Management

Jaewoo Kim (KAERI), Young-Soo Seo (Sejong Univ), Jeseung Yoo (KAERI, Sejong Univ), William H. Miller (Univ of Missouri, Columbia)

A Gamma Dose Rate Estimation Model For Radioactive Waste Containers

Maritza R. Gaul (CDTN), Massimo Zucchetti (DENERG)

Light Transport in Thin Polymeric Detectors with GEANT4 for Radiation Portal Monitors

M. J. Urffer, L. F. Miller (Univ of Tennessee-Knoxville)

A Verification of MCNP6 FMESH Tally Capabilities

Alicia L. Swift, Edward A. McKigney, Richard C. Schirato, Alex P. Robinson, Brian A. Temple (LANL)

Function of XRCC4 C-terminal Region in DNA Double-Strand Break Repair

Rujira Wanotayan, Mukesh Kumar Sharma, Yoshihisa Matsumoto (Tokyo Inst. of Technology)

Making Ethics Real in Nuclear Engineering–Panel

Computational Tools for Radiation Protection and Shielding

Development and Verification of the Fixed Source Photon Transport in RMC Code

Xiao Fan (Peking Univ, Tsinghua Univ), Kan Wang (Tsinghua Univ), Guohui Zhang (Peking Univ)

A New Stochastic Global Optimization Method for Inverse Transport Problems

Jerawan C. Armstrong, Jeffrey A. Favorite (LANL)

Status on the Development of a Monte Carlo Methods Research Framework

Alex Robinson (Univ of Wisconsin-Madison), Brian Kiedrowski (LANL), Douglass Henderson (Univ of Wisconsin-Madison)

PyNE Progress Report

Cameron R. Bates (LLNL, Univ of California-Berkeley), Elliott Biondo (Univ of Wisconsin-Madison), Kathryn Huff (Univ of California-Berkeley), Kalin Kiesling, Anthony Scopatz, Robert Carlsen, Andrew Davis, Matthew Gidden, Tim Haines (Univ of Wisconsin-Madison), Joshua Howland, Blake Huff (Univ of California-Berkeley), Kevin Manalo (Georgia Tech), Arielle Opotowsky (Univ of Wisconsin-Madison), Rachel Slaybaugh (Univ of California-Berkeley), Eric Relson (Univ of Wisconsin-Madison), Paul Romano (MIT), Patrick Shriwise (Univ of Wisconsin-Madison), John D. Xia (Univ of Chicago), Paul Wilson, Julie Zachman (Univ of Wisconsin-Madison)

Quality Assurance within the PyNE Open Source Toolkit

Elliott Biondo, Anthony Scopatz, Matthew Gidden (Univ of Wisconsin-Madison), Rachel Slaybaugh, Cameron Bates (Univ of California-Berkeley), Paul P. H. Wilson (Univ of Wisconsin-Madison)

MCNP6 Enhancements to Alpha Particle Production and Transport

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

Radiation Protection and Shielding–Roundtable

Introduction to the SCALE/MAVRIC Shielding Tools–Tutorial

Reactor Physics: General—I

Assessment of an On-Line Reactivity Monitoring Technique

Dominic Caron, Sandra Dulla, Marta Nervo, Piero Ravetto (Politecnico di Torino), Mario Carta (ENEA C.R. CASACCIA)

Neutron Deterministic Models of the EBR-II HRT-45R Core Configuration

Marco Marchetti, Barbara Vezzoni, Fabrizio Gabrielli, Andrei Rineiski (Karlsruhe Inst. of Technology)

Thermal Nuclear Reactor Control by Moderator Displacement with Negative Feedback

Neal L. Mann (Univ of Pittsburgh)

Fully Ceramic Microencapsulated Fuel in FHRs: A Preliminary Reactor Physics Assessment

Jeffrey J. Powers (ORNL)

Reduction of Spatial and Spectral Effects by Adjoint Weighing of Flux Signals in a Reactivity Reconstruction Technique

Sandra Dulla, Siew Sin Hoh, Marta Nervo, Piero Ravetto (Politecnico di Torino)

Statistical Error Estimation Using Bootstrap Method for the Feynman-alpha Method

Tomohiro Endo, Takeshi Shizawa, Akio Yamamoto (Nagoya Univ), Cheol Ho Pyeon, Takahiro Yagi (Kyoto Univ)

Application of the Big T Burnable Absorber to AP1000 Core for a Soluble Boron Free Operation

Mohd-Syukri Yahya, Yonghee Kim (KAIST)

Reactor Physics: General—II

Initial Verification of Heterogeneous Multigroup Cross Sections in MC2-3/PROTEUS

Jacob S. Hader (Purdue Univ), Emily R. Shemon, Changho Lee (ANL)

Watts Bar Unit 1 MCNPX Simulations with KENO-VI Comparisons

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

The Asymptotic Probability Distribution of Fission Numbers in a Multiplying System

Erin D. Fichtl (LANL), Anil K. Prinja (Univ of New Mexico)

The Preliminary Application of Coupled Point Kinetic Model for TMSR Safety Analysis

Jun Cai, Xiaobin Xia, Kun Chen, Mudan Mei, Jianhua Wang, Guoqing Zhang (Chinese Academy of Sciences)

Comparison of Doppler Reactivity between Thorium and Uranium Fuels in LWR

Noboru Dobuchi, Takuya Mishiro, Takanori Kitada (Osaka Univ)

Modernization and Expansion of Isotopic Depletion Capabilities within the NESTLE 3D Nodal Simulator

P. Eric Collins, Nicholas Luciano, G. Ivan Maldonado (Univ of Tennessee-Knoxville)

Evaluation of an Integral Homogenization Approach for LWSMR Core Neutronics Discretization

Ahmad Al Rashdan, Pavel Tsvetkov (TAMU)

Reactor Physics: General—III

The Development of the Variational Nodal Method

E. E. Lewis (Northwestern Univ), invited, Eugene P. Wigner Reactor Physicist Award Lecture

Validation of Updated Resonance Reconstruction Module of RXSP Code Based on R-Matrix Limited Formula

Jiankai Yu, Wanlin Li, Kan Wang (Tsinghua Univ)

Preliminary Assessment of nTRACER and McCARD Direct Whole Core Transport Solutions to VERA Core Physics Benchmark Problems

Min Ryu, Hyun Ho Cho, Chang Hyun Lim, Yeon Sang Jung, Han Gyu Joo (Seoul National Univ)

Neutronics Analyses for an LEU Core for TREAT

Dimitrios C. Kontogeorgakos, Heather M. Connaway, Arthur E. Wright, Gokhan Yesilyurt, Keith L. Derstine (ANL), Mark D. DeHart, Sean R. Morrell (INL)

Flexible Uncertainty Analysis of Computer Models with Alchemy

Jason M. Hite, Congjian Wang, Bassam Khuwaileh, Hany S. Abdel-Khalik (NCSU)

Preliminary Investigation of Fission and Surface Source Iteration Scheme in Domain Decomposition Method for Whole-Core Monte Carlo Calculation

YuGwon Jo, Nam Zin Cho (KAIST)

Advances in Fast Reactor Designs and Concepts

EBR-II Passive Safety Demonstration Tests Benchmark Analyses – Phase 1

L. L. Briggs, T. Sumner, T. Fei, T. Sofu (ANL), S. Monti (IAEA)

On Multi-Group Cross Sections for Breed-and-Burn Reactors

Jason Hou (Univ of California-Berkeley), Florent Heidet (ANL), Phillip Gorman, Ehud Greenspan (Univ of California-Berkeley)

Calculation of Photon Heat Generation for EBR-II Using DIF3D/MC2-3

T. Fei, C. H. Lee, T. K. Kim, T. Sofu (ANL)

3D Shuffling in Breed and Burn Reactors

Staffan Qvist (Uppsala Univ), Ehud Greenspan (Univ of California-Berkeley)

Maximum Burnup of Breed and Burn Reactors with Limited Separation Processes

Christian D. Di Sanzo, Ehud Greenspan, Jasmina L. Vujic (Univ of California-Berkeley)

An Investigation on the Homogenization of Fast Reactor Fuel Assembly

Woong Heo, Yonghee Kim (KAIST)

Reactor Physics Design, Validation, and Operating Experience

Direct Imaging of a Godiva IV Burst at NCERC

J. D. Goettee, E. I. Esch, J. M. Goda, D. K. Hayes, D. R. Mayo, W. L. Myers (LANL)

Similarity Assessment of the BFS-109-2A Axial Expansion Experiment Using a Novel Jacobian Matrix Method

Sunghwan Yun, Sang Ji Kim (KAERI)

Burst Initiation Probability Experiments at CFBR-II

Liu Xiaobo, Peng Xianjui, Lei Jiarong (China Academy of Engineering Physics)

Determination of Bias, Bias Uncertainty, and Coverage using Data Assimilation

Paridhi Athe (NCSU), Ugur Mertyurek (ORNL), Hany S. Abdel-Khalik (NCSU)

Three-Dimensional Modeling of the Physics of the Transient Reactor Test (TREAT) Facility

Joseph Templeton, Mario Ortega, Cassiano de Oliveira (Univ of New Mexico)

Physics and Engineering Analysis of Sub-Critical Driven Systems—I

A Laser Fusion Thorium Breeding Reactor

Sümer Şahin (Atlim Univ), Başar Şarer, Yurdunaz Çelik (Gazi Univ)

Studies of Gas-Cooled Pressure-Tube Blanket Lattices for Hybrid Fusion-Fission Reactors with Thorium-Based Fuels

Blair P. Bromley (AECL)

Neutronic Analysis on Coolant Options in a Hybrid Reactor System for High Level Waste Transmutation

Seong-Hee Hong, Myung Hyun Kim (Kyung Hee Univ)

Conceptual Design of an Accelerator-Driven Subcritical System to Dispose the Minor Actinide Fuels

Yan Cao, Yousry Gohar, Elia Merzari, Adam R. Kraus (ANL)

Preliminary Neutronic Study of An MIT Reactor Driven Fluoride-salt-cooled Sub-critical System

Kaichao Sun, Lin-wen Hu, Charles Forsberg (MIT)

Physics and Engineering Analysis of Sub-Critical Driven Systems—II

Concerning Am-241 Incineration in the Nuclear Power Installations

Georgy Khorasanov, Anatoly Blokhin (Obninsk Inst. for Nuclear Power Engineering)

Reactivity Measurements in Subcritical Assemblies Combining MSM and Area Methods

A. Talamo, Y. Gohar (ANL), S. Sadovich, H. Kiyavitskaya, V. Bournos, Y. Fokov (Joint Inst. for Power and Nuclear Research-SOSNY, Minsk)

Impact of MAs Loading on Transient Characteristics of ADS System

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

Approach-to-Critical with the Idaho State University Sub-Critical Assembly Using The Modified Source Method

Andrew Layne, Chad Pope (Idaho State Univ)

Accelerator-Based Neutron Source to Drive Sub-Critical Systems

Ross Radel, Greg Piefer, Evan Sengbusch (Phoenix Nucl Labs)

Design and R&D Activities of Subcritical Reactors to Support Nuclear Fuel Cycle of China

Yican Wu, FDS Team (Chinese Academy of Sciences)

New Nuclear Data Formats and Processing Capabilities

Nuclear Data Processing at LANL with NJOY – Past, Present and Future

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

INSURE: An Inverse Sensitivity Uncertainty Quantification Toolkit

Congjian Wang, Bassam A. Khuwaileh, Hany S. Abdel-Khalik (NCSU), Goran Arbanas, Mark L. Williams, Michael E. Dunn (ORNL)

Core Design Perspective on Accident Tolerant Fuels

Systematic Study of a Small, Long-life HTGR Design for Passive Decay-Heat Removal

Odmaa Sambuu, Toru Obara (Tokyo Inst. of Technology)

Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in Light Water Reactors

Nathan M. George (Univ of Tennessee-Knoxville), Jeffrey J. Powers (ORNL), G. Ivan Maldonado, Kurt A. Terrani, Andrew Worrall (Univ of Tennessee-Knoxville)

Uranium Nitride Composite Fuels in a Light Water Reactor: Advanced Cladding, Nodal Core Calculations, and Transient Analysis

Nicholas R. Brown, Lap-Yan Cheng, Michael Todosow (BNL)

Reactor Physics Analysis Methods—I

Sensitivity/Uncertainty Analysis of Mean Generation Time with Deterministic Codes

Gerardo Aliberti, Micheal A. Smith (ANL)

Development of Online Core Monitoring Methodology applying Periodic 3DPCM for KSNP

Wi-Soo Jeong, Hae-Chan Lee, Hyeong-Seog Kim, Chang-Kue Lee, Sang-Weon Park (KEPCO)

Evaluation of Effective Delayed Neutron Fraction Techniques in MC21

Stephanie A. Kempf, Timothy H. Trumbull (Bechtel Marine Propulsion Corp)

Intersection Subspace Method for Uncertainty Quantification

Congjian Wang, Jason Hite, Hany S. Abdel-Khalik (NCSU)

Modeling an iPWR Startup Core Cycle with VERA

Kelly Kenner (Univ of Tennessee-Knoxville), Rose Montgomery (TVA), G. Ivan Maldonado (Univ of Tennessee-Knoxville)

Estimation of Sensitivity Coefficient using Random Sampling and L1-norm Minimization

Tomoaki Watanabe, Tomohiro Endo, Akio Yamamoto (Nagoya Univ), Yasuhiro Kodama, Yasunori Ohoka, Tadashi Ushio (Nuclear Fuel Industries, Ltd.)

Reactor Physics Analysis Methods—II

Resonance Self-Shielding Method with Resonance Interference Factor Library

Sooyoung Choi, Azamat Khassenov, Deokjung Lee (UNIST)

TDKENO: A Hybrid Time-dependent Transport Analysis Tool

Sedat Goluoglu, Justin Paluch (Univ of Florida), Mark DeHart, Sean Morrell (INL)

Comparison of Spatial Source Expansion Methods in the Three Dimensional Transport Method LEAF

Yuki Kato, Tomohiro Endo, Akio Yamamoto (Nagoya Univ)

Improvements to the SP3 Discontinuity Factors in PWR Pin-by-pin Calculation

Yunzhao Li, Bin Zhang, Hongchun Wu, Liangzhi Cao (Xi’an Jiaotong Univ)

Fuel Pin Problem Solution via an Accelerated COMET Method

Kyle Remley, Farzad Rahnema (Georgia Tech)

Impact of Improved Experimental Uncertainty Quantification on the Evaluated ²³⁹Pu Prompt Fission Neutron Spectrum

Denise Neudecker, Patrick Talou, Toshihiko Kawano (LANL)

Physics of Compact Reactors for Terrestrial and Space Applications

Nuclear Demonstration Test Design for the KiloPower Space Reactor

Patrick McClure, David Poston (LANL), Marc Gibson (NASA Glenn Research Center)

Full Submersion Criticality Accident for Low Enriched Uranium Nuclear Thermal Rockets

Paolo Venneri, Yonghee Kim (KAIST), Peter Husemeyer, Stephen Howe (USRA)

Moose Multi Physics–Tutorial

Tutorial on Radiation Protection and Shielding in Aeronautics and Space Applications

General Thermal Hydraulics—I

Thermal-Hydraulic Core Design Concept of an Accelerator-Driven Minor Actinide Burner

Adam Kraus, Elia Merzari, Yan Cao, Yousry Gohar (ANL)

A Mechanistic Vertical Low Flow Critical Heat Flux Correlation

Jeffrey M. Luitjens, Qiao Qu (Oregon State Univ)

Validation Data: Managing the Weak Link

Nam Dinh (NCSU), Weiju Ren (ORNL), Hyung Lee (BAPL)

Benchmark data for CFD Validation using 2D-PIV in Turbulent Parallel Planar Jets

Elvis Dominguez-Ontiveros, Hristo Goumnerov, Yassin Hassan (TAMU)

Sensitivity Analysis of Fukushima Daiichi Unit 1 Type Accident with MELCOR

Gen Li (Waseda Univ), Yoshiaki Oka (Univ of Tokyo)

Tank Mixing Study with Flow Recirculation

Si Y. Lee (SRNL)

Thermal-Hydraulically Optimal Power Profile for a Nuclear Thermal Rocket Engine

Peter J. A. Husemeyer (Univ of Cambridge, Center for Space Nuclear Research)

Preliminary Design of a Helical Coil Heat Exchanger for a Fluoride Salt-Cooled High-Temperature Test Reactor

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

General Thermal Hydraulics—II

Study on Natural Circulation and Its Transition Process for IP200

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

Assessment of Parallel Algorithms for a Subchannel Code MATRA

Seong Jin Kim, Hyouk Kwon, Dae Hyun Hwang (KAERI)

Thermal Solar Collector Predictive Modeling: I. Adjoint Sensitivity Analysis

Dan G. Cacuci (Univ of South Carolina), A. F. Badea (Karlsruhe Inst. of Technology), M. C. Badea (Univ of South Carolina)

Thermal Solar Collector Predictive Modeling: II. Data Assimilation, Model Calibration, and Best-Estimate Predictions with Reduced Uncertainties

A. F. Badea (Karlsruhe Inst. of Technology), Dan G. Cacuci, M. C. Badea (Univ of South Carolina)

Mechanistic Modeling of Heat Transfer in Supercritical Carbon Dioxide

Jianguo Zhong, M. Z. Podowski (RPI)

Experimental Support for System Code Development and Validation: IETs and SETs–Panel

Computational Thermal Hydraulics—I

CFD Modeling of Heat and Mass Transfer in Heat Exchangers of Sodium-Cooled Fast Reactor Systems

Emre Tatli, Milorad B. Dzodzo, Paolo Ferroni (Westinghouse)

A Novel Approach on Modeling Fluid-Structure Interactions for a Fuel Plate

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

Direct Numerical Computation of Lift Force in Low Viscosity Fluid

Zhongchun Li (Tsinghua Univ), Xiaoming Song (Nuclear Power Inst. of China), Shengyao Jiang (Tsinghua Univ)

A Code Verification Method for Governing Equations of Two-Fluid Model

Hao Zhang, Zhao Guo Wu, Yi Xue Chen (SNPSDC)

CORONA Analysis with Consideration of Bypass Flow Gap Size Distribution

Nam-il Tak, Sung Nam Lee, Min Hwan Kim, Jae Man Noh (KAERI)

Thermal Predictions of the Cooling of Waste Glass Canisters

Donna Post Guillen (INL)

Development of the Code COAC for Oxidation during Core Melting

Keyou Mao, Yapei Zhang (Xi’an Jiaotong Univ), Michael L. Corradini (Univ of Wisconsin-Madison)

RELAP RCIC Pump Homologous Curves Generation and Verification for Fukushima Unit 2

Hector Lopez, Nejdet Erkan, Okamoto Koji (Univ of Tokyo)

Computational Thermal Hydraulics—II

Application of the Entropy Viscosity Method to the 1-D7-Equation Model for Two-Phase Flows

Marc O. Delchini, Jean C. Ragusa, Ray A. Berry (TAMU)

Thermal Hydraulic Effects of 3-D Power Variations in a PWR Fuel Pin using CFD

Daniel Walter, Victor Petrov, Annalisa Manera (Univ of Michigan)

A Multiscale CFD/1D-TH Coupling Overlapping Domain Methodology for Thermal Hydraulic Systems

Timothy P. Grunloh, Annalisa Manera (Univ of Michigan)

Emergency Core Cooling System Sensitivity Analysis for a Four-Loop Pressurized Water Reactor with Three Independent Injection Trains

Timothy Crook, Rodolfo Vaghetto, Alessandro Vanni, Yassin A. Hassan (TAMU)

Stabilization Techniques for Simulation of High-Aspect Ratio Fluid Structure Interaction (FSI) Models of Flat Plates Under Variable Velocity Parallel Flow

Casey J. Jesse, John C. Kennedy, Gerhard H. Schnieders, Gary L. Solbrekken (Univ of Missouri)

Two-Phase Flow Modeling of Steam Direct Contact Condensation as Support of the Fukushima Daiichi Accident Investigation

Marco Pellegrini, Masanori Naitoh (Inst. of Applied Energy)

Development of 3D Containment Simulation Capability: High Pressure Steam Blowdown Scenario

Botros Hanna, Nam Dinh, Igor Bolotnov (NCSU)

Numerical Study on Single Droplet’s Rise in Steam Separator by Using VOF Method

Di Zhang (Tsinghua Univ, Nuclear Power Inst. of China), Qi Luo, Wei Huang (Nuclear Power Inst. of China), Kan Wang (Tsinghua Univ)

Computational Thermal Hydraulics—III

Multidimensional Modeling of Force Convection Subcooled Boling in Pressurized Water Reactors

Dillon Shaver, Michael Z. Podowski (RPI)

Incorporation of MELCOR with CTI’s Calvert Cliff’s Simulator Product

Robert Sanders (AREVA), Barney Panfil (CORYS Thunder, Inc.)

Comparison of Two-Temperature Homogenized Model, Harmonic- and Volumetric-Average Thermal Conductivity Models on Transient Analysis of Fully Ceramic Microencapsulated Fuel

Yoonhee Lee, Nam Zin Cho (KAIST)

Modeling and Simulation of Solid Fluidization in a Resin Column

Si Y. Lee (SRNL)

TRACE Code Calculations of MIT Pressurizer Tests for Review of SPACE Code Capability

Chanyi Song, Young Seok Bang, Andong Shin, Sweng-Wong Woo (Korea Inst. of Nuclear Safety)

Optimal Meshing Methods and Schemes for the Simulation of Assembly

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

Experimental Thermal Hydraulics—I

Design and Assembly of Experimental Facility for CRUD Characterization and Mitigation at PWR Cladding Conditions

Ittinop (Pun) Dumnernchanvanit, Naiqiang Zhang, Alexandra R. Delmore, Michael P. Short (MIT)

Compression of Fibrous Porous Media Generated on Containment Sump Strainers

Saya Lee, Matthew Kappes, Yassin A. Hassan (TAMU)

Size Characterization of Fibrous Nukon Debris Upstream and Downstream of the Containment Sump Strainer

Matthew Kappes, Saya Lee, Yassin A. Hassan (TAMU)

Interfacial Shear Measurement of a Wavy Gas-Liquid Interface

Matthieu A. Andre, Philippe M. Bardet (George Washington Univ)

CHF Study on Effect of Wettability under Pressurized Condition for Downward Facing Surface

Hae Min Park, Yong Hoon Jeong (KAIST)

High Pressure Condensation in Small Modular Reactor Containments

Etienne Mullin (Oregon State Univ), Claudio Delfino (NuScale Power LLC), Qiao Wu (Oregon State Univ), Jose Reyes (NuScale Power LLC)

Experimental Study of Twin Turbulent Parallel Jets using an Open-Source Three Dimensional Particle Tracking Velocimetry Software

Elvis Dominguez-Ontiveros, Hristo Goumnerov, Yassin Hassan (TAMU)

Experimental Thermal Hydraulics—II

Investigation of Flow Laminarization and Heat Transfer Reduction in a VHTR Reactor Core

Francisco I. Valentin, Narbeh Artoun (City College of New York), Hitesh Bindra (KSU), Masahiro Kawaji (City College of New York, CUNY Energy Inst.)

Pressurized Startup Transient Analyses for the BWR-type NMR-50

Shanbin Shi, Caleb Brooks, Jaehyuk Eoh, Mamoru Ishii (Purdue Univ)

Downward-Facing Subcooled Flow Boiling with Extended Surface

Abdul R. Khan, Nejdet Erkan, Koji Okamoto (Univ of Tokyo)

Experimental Study of Advanced IVR-ERVC Strategy with Liquid Metal Coolant

Seong Dae Park, In Cheol Bang (UNIST)

Development of Optical Fiber Sensors for use in Sodium Cooled Reactor Instrumentation

Matthew Weathered, Dr. Mark Anderson (Univ of Wisconsin-Madison)

Experimental Thermal Hydraulics—III

Design of a Scaled Experimental Facility for the NGNP Reactor Cavity Cooling System

Thien Nguyen, Victor Petrov, Annalisa Manera (Univ of Michigan)

Matched-Index-of-Refraction Flow Facility for Fundamental and Applied Research

Piyush Sabharwall, Carl Stoots, Donald M. McEligot, Richard Skifton, Hugh M. Mcllroy (INL)

CCFL of Steam-Condensate Two-Phase Flow in a U-tube

Takahiro Nozue, Yuki Fujii (Kobe Univ), Michio Murase (Inst. of Nuclear Safety System), Kosuke Hayashi, Shigeo Hosokawa, Akio Tomiyama (Kobe Univ)

A Multi-Purpose Thermal Hydraulic Test Facility For Support of Advanced Reactor Technologies

James E. O’Brien, Piyush Sabharwall, SuJong Yoon (INL)

Thermal Hydraulics Analyst 2.1–Panel

Young Professional Thermal Hydraulics Research Competition

On High Order Numerical Schemes for 1-D Fluid Model

Ling Zou, Haihua Zhao, Hongbin Zhang (INL)

SFR Duct Wall Temperature Prediction with a Porous Medium Model

Yiqi Yu, Elia Marzari, J. Thomas (ANL)

On the Natural Frequency of Fueled Experimental Plates in Air and Water – Experimental Study

P. L. Harmon, Wade R. Marcum, S. Liu, M. Moussaoui, A. Weiss (Oregon State Univ), W. F. Jones, N. Woolstenhulme (INL)

On the Natural Frequency of Fueled Experimental Plates – Numerical Study

K. Britsch, Wade R. Marcum, T. K. Howard, P. L. Harmon (Oregon State Univ)

Development of Bubble Tracking Capability for Level-Set Interface Tracking Method

Jun Fang, Igor A. Bolotnov (NCSU)

Modeling Fuel Assemblies on Large Shake Tables

Noah A. Weichselbaum, Morteza Rahimi-Abkenar, Majid Manzari, Philippe M. Bardet (George Washington Univ)

A Numerical Approach to Solve Governor Equations of a System Code

Zheng Fu, Fatih Aydogan (CAES)

Deterministic Computational Methods for Radiation Transport and Dosimetry in Physics and Radiation Shielding

Towards “Virtual” Intra-operative SPECT or PET Guided Surgery: Advances in Image Reconstruction and Registration Using Deterministic Radiation Transport Simulation

Ian Marsh (Univ of Wisconsin-Madison, Univ of Wisconsin-La Crosse), Brayan Bednarz (Univ of Wisconsin-Madison)

Deterministic Simulation of Radiation Dose in X-ray Computed Tomography

Edward T. Norris, Xin Liu (Missouri Univ of Science and Technology)

Radiation Dose Assessment Based on Voxel Phantom during Reactor Spallation Target Replacement

Ting Li, Tao He, Liqin Hu, FDS Team (Chinese Academy of Sciences)

CAD-based Point Kernel Integral Method for Real-time Radiation Dose Assessment

Jie Wang, Jing Song, Liqin Hu, FDS Team (Chinese Academy of Sciences)

Computer Aided Diagnosis of Oral Cancer: Using Time-Step CT Images

Jonathan T. Scott (Missouri Univ of Science and Technology)