Annual Meeting 2019 / Volume 120

Table of Contents

Author Index

Full Issue

Opening Plenary: The Value of Nuclear

Timothy O'Connor (Xcel Energy)

ANS President’s Special Session: Popping the Nuclear Bubble—A Facilitated Conversation with Minnesota’s Utility Community

John E. Kelly (Individual)

General Chair's Special Session

Timothy O'Connor (Xcel Energy)

Operability Evaluation of Residual Heat Removal Pump for Full System Decontamination of Kori-1 Nuclear Power Plant

Hak-Soo Kim, Cho-Rong Kim (KHNP)

The RESRAD Code Applications for Radiological Safety Analysis of Nuclear Power Plants Decommissioning

Huai-En Hsieh, Hui-Fang Miao (Xiamen Univ.), Wen-Yu Wang, Yen-Cheng Liu, Bau-Shei Pei (Tsing Hua Univ.)

Experimental Investigation of Partitioning Ratio of Co Between Ingot and Slag after Melting Process of Radioactive Metal Waste

Byum Kyu Kim, Hwajeong Han, Byung Gi Park (Soonchunhyang Univ.), Bongsoo Lee (Chung-ang Univ.)

Water Technologies and Nuclear Power Update–Panel

Leah Parks (NRC)

License Transfers for Decommissioning–Panel

Gerard P. van Noordennen (Energy Solutions)

Decommissioning Experience in the Midwest–Panel

James J. Byrne (Byrne & Associates)

Teaching the Value of Nuclear—Nuclear Science and Facilities–Panel

Lisa M. Marshall (NCSU)

Nuclear Science Training for Secondary School Teachers at Argonne National Laboratory

David Grabaskas, Sunaree Hamilton, Natalie Zender (ANL)

Nuclear Power Technology Training Based on Mixed Reality Technology

Yifen Chen, Jianxiang Zheng, Huai-En Hsieh, Yichun Wu (Xiamen Univ.)

New Toys and Tricks for Old Dogs

Rizwan-uddin (Univ. Illinois)

Training Management and the Workforce: How to Recognize and Arrest Performance that is Indicative of Multiple/Repetitive Degraded Cornerstone Column (Column 4) Plants

Gary R. Cavanaugh (Marathon Consulting)

Addressing Fears of Nuclear Through Free-Choice Learning

Jonathan Gomez (Y-12)

How to Effectively Manage Public Communications and Outreach in Support of Nuclear Energy Related Issues

Scott D. Northard (Due North Energy Consulting)

Examining the Role of Cultural Value on Nuclear Acceptance in China

Dongqin Xia, Yazhou Li, Yanling He, Tingting Zhang, FDS Team (Inst. Nuclear Energy Safety)

Communication Challenges for the Nuclear Industry in the Era of Fake News and Social Media

P. Thakur (CEMRC), A. L. Ward (U.S. DOE)

Focus on Communications: Meanwhile in Canada—How Communications Helped the Nuclear Industry to Expand—I–Panel

Mimi H. Limbach (Potomac Communications)

Focus on Communications: What are Your Non-Nuclear Friends REALLY Thinking?—II –Panel

Margaret Harding (4 Factor Consulting)

MATLAB PDE Toolbox for Neutron Diffusion Equation

Xue Yang (Texas A&M, Kingsville)

Automated Remote Control for Detector System on USMA Subcritical Assembly

Kenneth S. Allen, Samantha Hartman, Garrett Sexton, Robert Thomas (USMA)

Seminars for Nuclear Science Public Education in Las Vegas, Nevada

Steven Curtis (ANS, Nevada Section)

Developing a Nuclear Science Merit Badge Workshop

Katherine Luebke (UNLV), Steven Curtis (ANS, Nevada Section)

The WIPP 20th Anniversary–Panel

Jean-Francois Lucchini (LANL)

Dynamic Sorption Studies of Organoiodine Species on Silver-Mordenite

Tejaswini Vaidya, Vivek Utgikar, Krishnan Raja (Univ. Idaho), Piyush Sabharwall (INL)

Kinetic Study of Ag?Z and Ag?-Aerogel Aged in Off-Gas Streams from Spent Nuclear Fuel Reprocessing System

Seungrag Choi, Yue Nan (Syracuse), Alexander Wiechert, Austin P. Ladshaw, Sotira Yiacoumi (Georgia Tech), Costas Tsouris (Georgia Tech & ORNL), Lawrence L. Tavlarides (Syracuse)

Extended Duration Adsorption of Elemental Iodine by AgZ Under Prototypical Vessel Off-Gas Conditions

R. T. Jubin, J. A. Jordan, S. H. Bruffey (ORNL)

Separation of Xenon from Krypton in UNF Reprocessing Off Gas

Amy K. Welty, Mitchell R. Greenhalgh, Troy G. Garn (INL)

Removal of Krypton from Nuclear Re-Processing Plants Using Metal Organic Frameworks

Praveen K. Thallapally, Michael Sinnwell (PNNL)

Life-Cycle Assessment of Small-Modular Nuclear Reactors Using Current U.S. Fuel Cycle

Kara Michelle Godsey, Lindsay Shuller-Nickles, Michael Carbajales-Dale (Clemson)

Safety Evaluation of a Spent Fuel Dry-Storage Canister with Various Fill Materials

Jeremy W. King, Sunil S. Chirayath, Eric E. Aboud, Victor M. Bautista, Patrick A. Behne, Heukjin Boo, Ryan D. Brownfield, Jim A. Chisholm, Katie M. Cook, Amanda C. Edwin, Hadyn M. Kistle, Patrick J. O'Neal, Ernesto A. Ordonez, Mariah M. Ramirez, Sidney A. Ricketts, Rainbow Y. Suh (Texas A&M)

Preliminary Evaluation of Low-Force Solid-State Technologies for Mitigation and Repair of Stress Corrosion Cracking in Stainless Steel Canister

Hwasung Yeom, Nickolas Pocquette, Evan Rocco, Frederick van Steenderen (U.W., Madison), Kenneth Ross (PNNL), John Kessler (J Kessler & Associates), Gary Cannell (Fluor), Jay Rozzi (Creare), Kumar Sridharan, Frank E. Pfefferkorn (U.W., Madison)

Bismuthate Behavior with Used Nuclear Fuel Species in Nitric Acid

Jeffrey D. Einkauf, Andrew J. Wilcox, Jonathan D. Burns (Texas A&M)

Comparison of DEHiBA and DHOA for Neptunium Separation

Jarrod M. Gogolski (Colorado School of Mines), Peter Zalupski, Dean Peterman (INL), Mark P. Jensen (Colorado School of Mines)

Design and Implementation of a Flowsheet Solvent Extraction Simulator

Taha Azzaouiy (Univ. Mass., Lowell), Kevin L. Lyonz (INL), Valmor F. de Almeida (Univ. Mass., Lowell)

Advances in Online Spectroscopic Monitoring for Application Throughout the Nuclear Fuel Cycle

Samuel A. Bryan (PNNL), Gilbert L. Nelson (College of Idaho), Amanda Lines (PNNL), Job Bello (Spectra Solutions)

Square Wave Voltammetry Analysis of Metal Ions in Molten Salt Reactors

Huan Zhang, Suhee Choi, Michael F. Simpson (Univ. Utah)

Use of Machine Learning with On-Line Monitoring Systems for Reprocessing

Benjamin B. Cipiti, Nathan T. Shoman (Sandia)

Fiber-Optic Laser-Induced Breakdown Spectroscopy in High Temperature/Radiation Environment

Yichen Zhao, Haori Yang (Oregon State)

Challenges Associated with Material Transport into and Waste Removal from Hot Cell R&D Facilities Worldwide–Panel

Stephen Napier (National Nuclear Lab)

An Update on the Operational Status of the Savannah River Site H-Canyon

Tracy Stover (Savannah River Nuclear Solutions)

Plans for Treatment of Research Reactor UNF at La Hague

Paul Murray, Sven Bader (Orano)

New Reconditioning Strategies for Spent Nuclear Fuel Rods

Craig Barnes, Jordan R. Travis, Breanna K. Vestal (U.T., Knoxville), Guillermo Daniel DelCul (ORNL), David F. McLaughlin (Westinghouse)

Gaseous Preparation of Zirconium Clad Nuclear Fuel for Recycling

Rick Demmer, Julia Tripp, Melissa Warner, Richard Tillotson, Amy Welty (INL), Lonnie Olson (INL, Retired)

Progress in Consolidated Interim Storage and Next Steps–Panel

Sven O. Bader (Orano)

The Importance of Future Fuel Cycle Options in Addressing Growing Worldwide Energy Demand–Panel

Fiona E. Rayment (National Nuclear Lab)

Prospects for a Commercial High-Assay Low Enriched Uranium Supply to Support Advanced Reactors and Advanced LWR Fuel Applications–Panel

Everett Redmond (NEI), Morris Hassler (Y-12/CNS)

On-Line Monitoring for Spectroelectrochemical Characterization of Uranium Within Molten Salts

Shirmir D. Branch, Amanda M. Lines, Gregg J. Lumetta, Samuel A. Bryan (PNNL)

Molecular Dynamics Simulations of Structures and Transport Properties of UCl3-NaCl Molten Salts

Bo Li (U.C., Riverside), Sheng Dai (ORNL), De-en Jiang (U.C., Riverside)

Electrochemical Corrosion Monitoring in Molten MgCl2-NaCl-KCl

Suhee Choi, Olivia Dale, Michael F. Simpson (Univ. Utah)

Thermodynamic Approach to the Chemical Degradation of Fly Ash-Blended Concrete: Case Study for Korean LILW Trench Type Repository

Sol-Chan Han, Jong-Il Yun (KAIST)

Updates on Borated Aluminum Cask Design for Onsite Used Fuel Storage

R. A. Borrelli (Univ. Idaho)

Investigation of Void Formations Using Neutron Measurements in Filler Materials for Dual-Purpose Canisters

Seung Min Woo, Shikha Prasad, Sunil Chirayath (Texas A&M)

Initial Study for De-Inventory of Spent Nuclear Fuel from the Kewaunee Site

Kevin J. Connolly, Matthew R. Feldman (ORNL), Ralph E. Best, Steven J. Maheras (PNNL), Don McGee, Sven O. Bader (Orano)

SEPHIS-ACM: A Step Forward in Separations Simulation

Tracy Stover (Savannah River Nuclear Solutions), Jeffrey Pike (SRNL)

Hydrodynamics of Extraction Devices: Residence Time Distribution in Centrifugal Extractors

Jarod Perko, Vivek Utgikar (Univ. Idaho), Kevin Lyon (INL)

Niowave’s Fuel Fabrication and Recycle for Domestic Radioisotope Production from Fission Fragments

Faisal Y. Odeh, Alex C. Bakken, John Diemer, Amanda K. Grimm, Terry L. Grimm, Nathan C. Johnson, Christine M. Krizmanich, Mayir Mamtimin, William A. Peters, Kristin A. Shannon, Milan Stika, Robert N. Wahlen (Niowave)

Understanding Nitrate Chemistry – The Key to Safer and More Efficient TRU Waste Acceptance

Paul B. Duval (LANL)

Numerical Simulation of Observed Plasma Asymmetries in Tokamaks

Shahab Ud-Din Khan (Pakistan Atomic Energy Commission), Salah Ud-Din Khan (King Saud Univ.), Riaz Khan (Pakistan Atomic Energy Commission), Song Yuntao (IPP CAS), Shahid Hussain (Pakistan Atomic Energy Commission)

Estimation of Eddy Current on Pakistan Metallic Spherical Tokamak

Shahab Ud-Din Khan, Riaz Khan, Zia Ur Rehman, Sehrish Shakir, Shahid Hussain (Pakistan Atomic Energy Commission)

Highlights of the 2019 NPIC-HMIT Conference: Instrumentation and Controls—I–Panel

Pradeep Ramuhalli (PNNL)

Highlights of the 2019 NPIC-HMIT Conference: Human Factors Engineering—II–Panel

Ronald L. Boring (INL)

Development of New Performance Shaping Factors’ Taxonomy for a Human Reliability Analysis

Seongkeun Kang, Poong Hyun Seong (KAIST)

An Approach to Multi-Unit Human Reliability Analysis: Application of SPAR-H

Jooyoung Park, Awwal Mohammed Arigi, Jonghyun Kim (Chosun Univ.)

Development of a Signal Reconstruction Model for NPPs Under Emergency Situation

Seung Geun Kim, Poong Hyun Seong (KAIST)

An Artificial Neural Network Based Anomaly Detection Algorithm for Nuclear Power Plants

Jason Hou, Kan Ni, Ayman Hawari (NCSU)

Nuclear Main Control Room Obsolescence & Cyber Security Regulations Are New Challenges to Overcome

Otto P. Fest (OTEK Corp.)

Niowave’s Domestic Radioisotope Production from Uranium and Radium

Amanda K. Grimm, Chase H. Boulware, Terry L. Grimm, William A. Peters, Mike A. Zamiara (Niowave)

Efficiency Optimization of a Positron Moderator Foil

Raed Alsulami, Mubarak Albarqi (Missouri S&T & King Abdulaziz City), S. Q. Jaradat (Higher Colleges Technol.), Joseph Graham, Shoaib Usman (Missouri S&T)

Neutron Depth Profiling Measurement for Borophosphosilicate Glass (BPSG)

Mubarak Albarqi, Raed Alsulami (Missouri S&T & King Abdulaziz City), Joseph Graham (Missouri S&T)

Application of Pb Isotopes in Uranium-Cobalt Mineralisation

Manny Mathuthu (North-West Univ.)

Data-Driven Methodology for Predicting Isotope Production at Material Testing Reactors

Jorge Navarro (ORNL), Josh Peterson-Droogh, Brian Gross (INL), Richard Howard (ORNL), Wilson Cowherd (Univ. Missouri), Carla Dwight (INL)

Qualification of U-10Mo Base Fuel Over Design Envelop of U.S. High Performance Research Reactor Using Mini-Plate Irradiation Testing in ATR

Margaret A. Marshall, Irina Glagolenko, Nicholas D. Meacham, Dong O. Choe, Paul E. Gilbreath, Grant L. Hawkes, Doug S. Crawford, Erik S. Rosvall, James D. Wiest (INL)

Neutronic Analysis of Mini-Plate Experiments in the ATR for High-Performance Research Reactor LEU Conversion

Paul Gilbreath, Dong O. Choe, Margaret A. Marshall (INL)

Thermal Model of Oxide Growth in Mini-Plate Experiments in the Advanced Test Reactor

Grant Hawkes, Dong O. Choe (INL)

Structural Safety Analysis Overview for the U.S. HPRR Mini-Plate (MP-2) Experiment

Erik S. Rosvall (INL)

Design of a Pressurized Fuel Rod Weld System

N. S. Oldham, C. C. Baker, B. P. Durtschi, D. E. Stacey (INL)

An Expert System to Assist Researchers with Nuclear Materials Experiment Design

Brenden J. Heidrich (INL), Jordan M. Argyle (Univ. Idaho)

Neural Network Coupled with MCNP for Neutron Depth Profiling

Mubarak Albarqi, Raed Alsulami (Missouri S&T, King Abdul Azziz City), Joseph Graham (Missouri S&T)

Activation and Decay Heat Calculations Supporting MIMIC Experiment Design in TREAT

John D. Bess, Connie M. Hill, James R. Parry, Nicolas E. Woolstenhulme, Colby B. Jensen (INL)

Overview of I2 Irradiation Deployment Activities in TREAT

N. Woolstenhulme, J. Bess, P. Calderoni, B. Heidrich, D. Hurley, C. Jensen, R. Schley, K. Tsai (INL)

MCNP Analysis of the Aqua-SETH Experiment in TREAT

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

State-of-the-Art Experimental Capabilities at the N.C. State PULSTAR Reactor

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

The Fission Accelerated Steady State Test (FAST) – A Revised Capsule Design for the Accelerated Testing of Advanced Reactor Fuels

Bryon Curnutt, Geoffrey Beausoleil (INL)

Novel Intermediate Conductivity Experiment (NICE) Capsules for Irradiated Fuel

Brian Durtschi, Charles Folsom, Bryon Curnutt, Nate Oldham, Dan Wachs (INL)

Compressible Metal Foils for Temperature Control During Irradiation

Christian M. Petrie, Padhraic Mulligan, Joel McDuffee (ORNL)

Finite Element Based Surrogate Modeling and Irradiation Capsule Optimization for Large-Scale Neutron Irradiation Campaigns

Padhraic L. Mulligan, Nesrin O. Cetiner, Ryan Gallagher, J. Wilna Geringer, Anne Campbell (ORNL), Martin van Staden (X-Energy)

Design and Encapsulation of Irradiation Experiments for Previously Irradiated Materials

Ryan C. Gallagher, Richard H. Howard (ORNL), Grant A. Bickel (CNL)

A Review of Molten Salt Irradiation Experiments

Joel McDuffee, Ken Thoms (ORNL)

Validation Efforts for the ATRC MC21 Model Using the Last Decade of Experiments

Josh Peterson-Droogh, Joe Nielsen, M. Rose Holtz, Nathan Manwaring (INL)

Examination of Corrosion Development in a Chloride Salt Irradiation Experiment

N. Dianne Bull Ezell, Joel McDuffee, Stephen Raiman, Dave Bryant, Josh Schmidlin (ORNL)

Irradiation Damage Behavior in Novel High-Entropy Carbide Ceramics

Fei Wang, Xueliang Yan (Univ. Nebraska), Lin Shao (Texas A&M), Michael Nastasi, Bai Cui (Univ. Nebraska)

Radiation Damage in High Entropy Alloys

Calvin Parkin, Michael Moorehead, Mohamed Elbakhshwan, Kumar Sridharan, Adrien Couet (U. W., Madison)

Evaluation of Nb-Rich Clustering in a Zr-1.0%Nb Alloy Following Kr2+ or Neutron Irradiation at 310 oC

S. B. Adisa (Univ. Idaho), J. Hu (ANL), M. J. Swenson (Univ. Idaho)

Nb Redistribution in Proton Irradiated Zr1.0Nb

Zefeng Yu, Adrien Couet (U. W., Madison)

TEM Study of Nickel Under In-Situ Helium/Krypton Dual-Beam Irradiation

Wei-Ying Chen, Meimei Li (ANL)

Development of the FaMUS Methodology for Quantify Materials Understanding and its Application to the NSUF Research Portfolio

Simon M. Pimblott and J. Rory Kennedy (INL)

EBSD Characterization of Metallic Nuclear Fuel

Fidelma Di Lemma, Daniel Murray, James Madden, Alex Winston, Cynthia Adkins, Jan-Fong Jue, Jason Harp (INL), Assel Aitkaliyeva (Univ. Florida), Dennis Keiser (INL)

Thermal-Hydraulics and Neutronics Overview of the DISECT Experiment

W. J. Williams (INL, Purdue), C. Hale (INL), E. Sikik (SCK-CEN), M. Sprenger (INL), G. Borghmans (SCK-CEN), D. M. Wachs (INL), S. Van den Berghe (SCK-CEN), M. A. Okuniewski (Purdue), T. Maddock (INL), B. Boer (SCK-CEN)

Thermal Transport Measurement of a UN/U?Si? Accident Tolerant Fuel Using a Square-Wave Pulse Thermoreflectance Technique

Scott C. Middlemas, Zilong Hua, W. Tanner Yorgason, Robert S. Schley, David H. Hurley (INL)

X-Ray Computed Tomography Analysis of Neutron-Irradiated SiC Composite Tube

Takaaki Koyanagi, Yutai Katoh (ORNL), Gyanender Singh (U. T., Knoxville), Christian M. Petrie (ORNL), Christian P. Deck (General Atomics), Kurt A. Terrani (ORNL)

Post-Irradiation Analysis at the Nanoscale of 14YWT after Neutron Irradiation (16.6 dpa) at 386?C and 412?C

Maria A. Auger (Univ. Carlos III de Madrid), David T. Hoelzer (ORNL)

Technological Aspects of MSR Fuel Cycle

Martin Straka (ÚJV ?ež), Jan Uhlí? (Res. Centre ?ež), Lórant Szatmáry (ÚJV ?ež), Martin Mare?ek (Res. Centre ?ež)

Compatibility Studies of Structural and Moderator Materials with Molten Chloride and Fluoride Salts

Stephen S. Raiman, Richard T. Mayes, J. Matthew Kurley, James R. Keiser, Nidia C. Gallego, Cristian I. Contescu, Dino Sulejmanovic, A. Lou Qualls (ORNL)

First-Principles Investigation on the Effect of Salt Species Adsorption on Cr Surface Segregation in Ni-Cr Alloys

J. K. Startt (Georgia Tech, ORNL), C. S. Deo (Georgia Tech), S. S. Raiman (ORNL)

Overview of General Atomics SiGA™ SiC-SiC Composite Development for Accident Tolerant Fuel

C. P. Deck, S. Gonderman, G. M. Jacobsen, J. Sheeder, S. Oswald, R. Haefelfinger, K. S. Shapovalov, H. E. Khalifa, J. Gazza (General Atomics), J. Lyons, P. Xu (Westinghouse), T. Koyanagi, C. Petrie (ORNL), C. A. Back (General Atomics)

Potential Impact of Accident Tolerant Fuel Thermal Properties on Rod Ejection and Small-Break Loss-of-Coolant Accidents

Robert F. Kile (U. T., Knoxville, Penn State), Aaron J. Wysocki, Andrew T. Nelson (ORNL), Nicholas R. Brown (U. T., Knoxville)

Characterization of the Thermal Conductivities of UO? Fuel Pellets with Aligned Molybdenum Metal Particles

Dong Seok Kim, Dong-Joo Kim, Sang-Chae Jeon, Keon Sik Kim, Jong Hun Kim, Ji-Hae Yoon, Jae Ho Yang (KAERI)

Oxidation of Cold Spray Cr Coatings in High Temperature Steam Environments

Hwasung Yeom, Tyler Dabney, Greg Johnson, Benjamin Maier, Kumar Sridharan (U. W., Madison)

Development of Cold Spray FeCrAl Coatings for Accident Tolerant Fuel

Tyler Dabney, Greg Johnson, Benjamin Maier, Hwasung Yeom, Kumar Sridharan (U. W., Madison)

Development of Cold-Sprayed Chromium Coatings for Accident Tolerant Fuel Cladding

Greg Johnson, Benjamin Maier, Tyler Dabney, Hwasung Yeom, Kumar Sridharan (U. W., Madison)

Successful Operation of the SNS Mercury Target at 1.4 MW

Mark Wendel, Drew Winder (ORNL)

Bison Metallic Fuel Modeling Capabilities

A. Casagranda, S. R. Novascone (INL)

High-Power Lead-Bismuth Targets and Material Studies

Robert N. Wahlen, Terry L. Grimm, Mayir Mamtimin, Faisal Y. Odeh, William A. Peters (Niowave), Stuart A. Maloy, Eric Olivas, Keith A. Woloshun (LANL)

Characterization of Annealed U-10Zr Fuel with Additive Antimony for Immobilizing Fission Product Lanthanides

Weiqian Zhuo (Virginia Tech), Michael T. Benson, Yi Xie, Robert D. Mariani (INL), Jinsuo Zhanga (Virginia Tech)

High Borated Molybdenum Alloyed Stainless Steels for Thermal Neutron Absorption

Tomáš Studecký (COMTES FHT)

Diffusion Behaviors Between Fe and Pd-Containing Metallic Fuel

Yi Xie, Michael T. Benson, Lingfeng He, James A. King (INL)

Aging of Aromatic Polyurethanes Bags for Nuclear Storage

Joseph H. Dumont, Eamonn Murphy, Drew Geller, Tristan M. Karns, Timothy A. Stone, Paul H. Smith, Kwan-Soo Lee, Andrea Labouriau (LANL)

Preliminary Characterization of RPV Materials Harvested from the ?Decommissioned Zion Unit 1 Nuclear Power Plant

Mikhail A. Sokolov, Thomas M. Rosseel, Randy K. Nanstad, Xiang Chen (ORNL)

Degradation Behavior of Fluoroelastomer under Simulated Severe Accident Environment

Inyoung Song (UNIST), Taehyun Lee, Kyungha Ryu (KIMM), In Cheol Bang, Ji Hyun Kim (UNIST)

First Tests of a Gamma-Blind Fast Neutron Detector Prototype Based on ZnS and Wavelength-Shifting Fibers

Alexander Wolfertz (ETHZ & PSI), Robert Adams (ETHZ), Grégory Perret (PSI)

In-Situ PWSCC Initiation Measurement of Nickel-Based Alloy Under Triaxial Stress State in Simulated PWR Water Environment

Seung Chang Yoo (UNIST), Kyoung Joon Choi (KAERI), Jong Sung Kim (Sejong Univ.), Ji Hyun Kim (UNIST)

Development of Cold Spray Process for Manufacturing of Oxide Dispersion Strengthened (ODS) Steel Cladding Tubes

Mia Lenling, Hwasung Yeom, Benjamin Maier, Greg Johnson, Tyler Dabney (U. W., Madison), Jeff Graham, Peter Hosemann (U. C., Berkeley), David Hoelzer (ORNL), Stuart Maloy (LANL), Kumar Sridharan (U. W., Madison)

Embedding Fiber-Optic Strain Sensors Using Ultrasonic Additive Manufacturing

Christian M. Petrie, Niyanth Sridharan (ORNL), Adam Hehr, Mark Norfolk (Fabrisonic), John Sheridan (Sheridan Solutions)

3D Printing Assisted 4H-SiC Schottky Diodes Fabricated for Alpha Particle Spectroscopy

Neil Taylor (Ohio State), Chaochao Dun, Mortaza Saeidijavash, Wenzheng Kuang, Yanliang Zhang (Notre Dame), Lei R Cao (Ohio State)

BISON Fuel Performance Simulations of TREAT Transients

David Kamerman, Nicolas Woolstenhulme, Colby Jensen, Dan Wachs (INL)

Effect of Interstitial Point Defect on Thermal Transport in Uranium Dioxide and Plutonium Dioxide

Katherine Mitchell, Alex Resnick, Jungkyu Park, Eduardo B. Farfán, Tien Yee, Andrew Hummel (Kennesaw State)

Current Issues in Computational Methods–Roundtable

David P. Griesheimer (Naval Nuclear Lab)

A Reduced-Order Neutron Diffusion Model Separated in Space and Energy via Proper Generalized Decomposition

Kurt A. Dominesey, Wei Ji (RPI)

Calculation of Parametric Variance Using Variance Deconvolution

Aaron J. Olson (Sandia)

Correlated Synthetic Time Series Generation Using Fourier and ARMA

Paul Talbot, Cristian Rabiti, Andrea Alfonsi, Cameron Krome, M. Ross Kunz, Aaron Epiney, Congjian Wang, Diego Mandelli (INL)

Conditional Point Sampling: A Novel Monte Carlo Method for Radiation Transport in Stochastic Media

Emily H. Vu (U. C., Berkeley, Sandia), Aaron J. Olson (Sandia)

Enhancements to the Discrete Generalized Multigroup Method

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

Angular Adaptivity with Filtered Pn Methods

S. Dargaville (Imperial College), A. G. Buchan (Queen Mary Univ.), R. P. Smedley-Stevenson (Imperial College, AWE), P. N. Smith (Imperial College, ANSWERS Software), C. C. Pain (Imperial College)

Weighted Average Calculation of the Method of Characteristics

Gil Soo Lee, Chae-Yong Yang (Korea Inst. Nucl. Safety) Adriaan Buijs (McMaster Univ.)

Rejuvenate Nuclear Technology Infrastructure and Facilities–Panel

Kevin H. Reynolds (Y-12)

Credible Accident Sequences in NCS–Panel

Lon E. Paulson (GE Hitachi)

Whisper Sensitivity Study of the NMIS ATR Fuel Storage Racks

K. M. Casanova (INL)

Investigating Region-Wise Sensitivities for Nuclear Criticality Safety Validation

Bobbi Merryman (Univ. New Mexico), Forrest Brown (Univ. New Mexico, LANL), Jennifer Alwin, Christopher Perfetti (LANL)

Preliminary TSUNAMI Assessment of the Impact of Accident Tolerant Fuel Concepts on Reactor Physics Validation

W. J. Marshall, J. Yang, U. Mertyurek, M. A. Jessee (ORNL)

A Method for Performing k?ff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS

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

Operational Reviews: How Facilities Meet ANSI/ANS-8.1 Section 4.1.6–Panel

Kristan M. Wessels (Y-12)

Excluding Benchmark Statistical Outliers in Nuclear Criticality Safety Validation

Jennifer Alwin, Forrest Brown (LANL)

Initial Investigations of the Criticality Safety Validation Basis for HA-LEU Transportation

B. T. Rearden, W. J. Marshall, J. B. Clarity, A. M. Holcomb, F. Bostelmann, J. M. Scaglione (ORNL)

Minimum Accident of Concern for Uranyl Sulfate Solutions

Joseph Christensen (SHINE Medical Technol.), R. A. Borelli (Center Advanced Energy Studies), Charles S. Henkel, Brian Matthews (Nucl. Safety & Technol. Services)

Performance of Nano-Fluids as Coolants/Moderator in APR1400 –Neutronics Case Study

Fatima I. Alhamadi, Rana Sadek, Amal Abdalla, Ahmed Ababneh, Zafar Said, Bassam A. Khuwaileh (Univ. Sharjah)

The Effect of Phase Disengagement on Criticality Safety Calculations for Aqueous Separations

Tracy Stover (Savannah River Solutions)

On the Use of Nature of Process Arguments

Tracy Stover, John Lint, Joshua Butler, Jaclyn Fitzpatrick (Savannah River Nuclear Solutions), Tara Smith, Kevin McCann (SRNL), Brett Clinton, Brittany Williamson (Savannah River Nuclear Solutions)

Carbon Reactivity Effect with Fissile Mass and Hydrogenous Moderation Control

Brandon M. O'Donnell (BWXT)

Mission Change from Enrichment to Deactivation Impact on Nuclear Criticality Safety

Tom Hines (PPPO), Matthew Wilson (Paschal Solutions), John Justice (Enercon), David Little (Fluor-BWXT), Brandon Little (Value Added Solutions)

Criticality Evaluation of SMART Fuel Storage with MCNP6

Sungwook Choi, Bon-Seung Koo (KAERI)

User Experiences with ICSBEP Distributed Sensitivity Data Profiles with the SCALE Sensitivity and Uncertainty Methods as of Winter 2019

Justin B. Clarity, William J. Marshall, Ellen M. Saylor (ORNL)

Validation of keff Calculations for Extended BWR Burnup Credit Calculations

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

Sharing of Good Industry Practices and/or Lessons Learned in Nuclear Criticality Safety–Panel

Deborah Ann Hill (National Nuclear Lab)

[Grand Challenge] Sodium Reactor Database to Support Knowledge Management–Panel

Matthew R. Denman (Kairos Power)

Safety Aspects of Accident-Tolerant Fuel Critical Heat Flux–Panel

Nicholas R. Brown (U. T., Knoxville)

A New Computational Tool for Rapid Uncertainty and Sensitivity Analysis of Sodium Reactor Source Term

David Grabaskas, James Jerden, Matthew Bucknor (ANL)

Protected and Unprotected Transient Performance and Sensitivity in a B&B Core

Chris Keckler (U. C., Berkeley), Thomas Fanning (ANL), Massimiliano Fratoni, Ehud Greenspan (U. C., Berkeley)

A Few Comparative Risk Lessons from WIPP

Norbert T. Rempe (Individual)

Risk-Informed Enhanced Resilient Plant Systems Analysis

Zhegang Ma, Hongbin Zhang (INL)

Hybrid Methodology of Deterministic and Probabilistic Safety Assessment Focusing on DSA

Bokyung Kim, Hee Cheon No (KAIST)

Radiological Accident Source Terms for LWRs: A Historical Perspective

Hossein Nourbakhsh (NRC)

Development of a Thermochemical Database for Sodium Fast Reactor Mechanistic Source Term Calculations

James Jerden, David Grabaskas, Matthew Bucknor (ANL)

Experimental Approach for the Effects of Various Iodines on Hydrogen Passive Autocatalytic Recombiner (PAR)

Hee-Jung Im, Jei-Won Yeon (KAERI)

Application of International Radiological Information Exchange (IRIX) Format for Radiation Monitoring Networks

Sanjoy Mukhopadhyay, Stephane Defour, Florian Baciu, Gurdeep Saluja, Jose Segarra (IAEA)

Monte Carlo Simulation of a Multisphere Neutron Spectrometer Based on CLYC Detector

Stuti Surani, Daniel Arizaga, Angela Di Fulvio (Univ. Illinois)

Highlights of 2019 ANS Probabilistic Safety Assessment and Analysis (PSA 2019)–Panel

Kevin R. O'Kula (AECOM Technical Services)

Key Regulatory Issues of Probabilistic Safety Analysis in Korea

Seungwoo Lee, Arryum Kin, Bogyung Kim, Dohyung Kim (Korea Inst. Nucl. Safety)

Nuclear Power Plant Evacuation: Gaps, Strategies, and Activity Scheduling

Adam Stein, Paul Fischbeck (Carnegie Mellon), Sola Talabi (Pittsburgh Technical)

On-Site Electrical Systems and Components Reliability Study in NPPs

Gary Wang (NRC), Zhegang Ma, Nancy Lybeck (INL), Don Marksberry, John Lane (NRC)

Coupling RAVEN to SAPHIRE for Performing Time Dependent Probabilistic Risk Assessment

C. Wang, D. Mandelli, A. Alfonsi, P. W. Talbot, S. T. Wood, J. K. Knudsen, C. Rabiti (INL)

Conversion of Miniature Neutron Source Reactors to Low Enriched Uranium Fuel

James A. Morman, Francesc Puig, John G. Stevens (ANL)

Japanese Plutonium Balance Outlook to 2050: A Monte Carlo Approach

Shutaro Takeda (Kyoto Univ.)

Investigation on Iran’s Nuclear Weapon Latency Time in Case of Non-Compliance with JCPOA

Kavita Rathore, Sunil S. Chirayath (Texas A&M)

Meeting Low-Carbon Industrial Heat Demand with High-Temperature Reactors Using Co-Generation and Heat Storage

Charles Forsberg (MIT)

Economic and Low-Carbon Incentives for Dispatchable Electricity From Base-load Reactors with Heat Storage

Charles Forsberg (MIT)

Potential of Chemical-Absorption Heat Pumps for Thermoamplification in Nuclear Hybrid Energy Systems

Paul D. Armatis (Oregon State), Aman Gupta (Univ. Idaho), Piyush Sabharwall (INL), Vivek Utgikar (Univ. Idaho), Brian M. Fronk (Oregon State)

Experimental Investigation and Analysis of Ca(OH)?/CaO Chemical Heat Pump for Thermal Energy Storage

Aman Gupta (Univ. Idaho), Paul D. Armatis (Oregon State), Piyush Sabharwall (INL), Vivek Utgikar (Univ. Idaho), Brian M. Fronk (Oregon State)

The Progress, Process and Value of a Zero Carbon Electric Generation Financial Futures Instrument

John K. Downing (John Downing Consulting)

Results of the April 2019 “Fastest Path to Zero” Summit and Unconference–Panel

Todd R. Allen (U. W., Madison)

Conceptual Design Considerations for KAIST Hybrid Micro Modular Reactor (H-MMR)

Jin Young Heo, In Woo Son, Ye Seul Kim, Jeong Ik Lee (KAIST)

Experimental Verification of the In-Vessel CEDM for Small Modular Reactors

Park Jinseok, Lee Wonho, Lee Myounggoo, Cho Yeonho, Kim Hyunmin, Maeng Chulsoo (KEPCO)

A Modular High-Temperature Gas-Cooled Reactor (MHTGR) with Decreased Power Density and In-Core Stored Heat for Variable Electricity and Industrial Heat

Charles Forsberg (MIT)

Economic Assessment of Nuclear Hybrid Energy Systems: Nuclear-Renewable-Water Integration in Arizona

Aaron S. Epiney, Cristian Rabiti, Paul Talbot, James Richards (INL)

Conceptual Design of China Lead-Based Mini-Reactor CLEAR-M10d

Zhumin Zhao, Liqin Hu, Yican Wu (FDS)

A Study of Passive Features of a Small Modular Reactor

Jun Chen, Huifang Miao, Huai-En Hsieh, Zhi'ao Huang (Xiamen Univ.), Xingwei Shi (Nucl. Radiat. Safety Center)

Floating Micro-Modular-Reactor Concept for Localized Power Outages

Kristin Smith, Pavel Tsvetkov, Moo-Hyun Kim, Lin Shao, Sunil Chirayath (Texas A&M)

Development of Frequency Response Function for ABWR

Shunsuke Konno, Junichi Kitamura (Hitachi-GE)

Financial Analysis of Modular Nuclear Reactors

Pedro Mena, Leslie Kerby (Idaho State)

First Assessment of the New Atomic Data Used in ENDF/B-VIII

Tullio Basaglia (CERN), Matteo Bonanomi, Federico Cattorini (Univ. Milano), Chansoo Choi (Hanyang Univ.), Min Cheol Han (INFN), Gabriela Ho? (Univ. Cagliari), Chan Hyeong Kim, Sung Hun Kim (Hangyang Univ.), Matteo Marcoli (Univ. Milano), Maria Grazia Pia, Paolo Saracco (INFN)

Electron Transport Algorithms in the Integrated TIGER Series (ITS) Codes

Brian C. Franke, Ronald P. Kensek (Sandia)

Monte Carlo Neutronics Analysis of the SNS STS Monolith

Igor Remec, F. X. Gallmeier (ORNL)

Adjoint-Enabled Multidimensional Optimization of Satellite Radiation Shields

Shawn Pautz, Don Bruss, Brian Adams, Brian Franke, Ethan Blansett (Sandia)

Evaluating Importance Maps for TRIPOLI-4® Using Deterministic or On-Line Methods

Davide Mancusi, Michel Nowak (CEA Saclay), Éric Dumonteil (IRSN), Henri Louvin, Emiliano Masiello, Daniele Sciannandrone (CEA Saclay)

SINBAD Database – Ongoing Activities

Ivan A. Kodeli (Jožef Stefan Institute)

Performance Study of Atomic Tally Methods For GPU-Accelerated Monte Carlo Dose Calculation

Tianyu Liu, Noah Wolfe, Hui Lin, Christopher D. Carothers, X. George Xu (RPI)

Effects of Statistical Uncertainty in Activation Calculations Based on Monte Carlo Radiation Transport

Jason Haverkamp (Naval Nuclear Lab)

Key Results of the ANS/HPS Conference on Low Level Radiation

Alan Waltar (Atomic Talk), Antone Brooks (DOE), Ludwig Feinendegen (Heinrich-Heine Univ.), Wanda Munn (Individual)

Neutron Spectrum Unfolding with a Planar Miniaturized Fast-Neutron Detector

Luke A. Stegeman, Quentin Pease, Tyler J. Hieber, Dipta Sarkar, Samuel W. Oxandale (Kansas State), Steven L. Bellinger (Radiation Detection Technologies), Zayd C. Leseman, Amir A. Bahadori (Kansas State)

Three-Dimensional Charge Distribution for Electrostatic Space Radiation Shielding

Rajarshi Pal Chowdhury, Luke Stegeman (Kansas State), Janet E. Barzilla (Leidos, NASA) Dan J. Fry, Ashish Goel (NASA), Matthew L. Lund (Univ. Utah), Stojan M. Madjunkov (NASA), Amir A. Bahadori (Kansas State)

Dissecting Air Secondary Gamma Dose Contribution for a 14 MeV Neutron Source in Air

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

Insulating Boron-Containing PDMS-Based Materials for Space and Nuclear Applications

Joseph H. Dumont, Eamonn Murphy, Kwan-Soo Lee, Andrea Labouriau (LANL)

Effects of Season, Altitude, and Areal Density on Neutron Transport in Air

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

Validation of the Shift Monte Carlo Code – Neutron Field Measurements in a Concrete Labyrint

Jackson N. Wagner (Texas A&M), Douglas E. Peplow (ORNL)

Comparison of MCCAD and DAGMC for Predictive Capability with BGA Inspection Systems

Michael P. Pfeifer, Nathanael Simerl (Kansas State), John Porter (Honeywell), Walter J. McNeil, Amir A. Bahadori (Kansas State)

Radiation Assessment of Nuclear Accident in the Greater Bay Area of China

Junjie Cai, Jiyun Zhao (City Univ. Hong Kong)

Comparing Two Methods for Approaching Nested DXTRAN Spheres as a Weight Shield

M. L. Fensin, K. C. Kelley, L. M. Rolison, E. S. Lum and S. S. McCready (LANL)

Validation of Shielding Analysis Capability of SuperMC3.3 with Dogleg Duct Streaming Experiment in FNS

Jun Zou, Bin Wu, Lijuan Hao, Jing Song, Pengcheng Long (Inst. Nucl. Energy Safety Technol.)

Derivative of an (?,n) Neutron Source with Respect to Nuclear Data

Jeffrey A. Favorite (LANL)

Overview of the Versatile Test Reactor—I–Panel

Florent Heidet (ANL)

Overview of the Versatile Test Reactor Core Design Activities

Florent Heidet (ANL), Gilles Youinou (INL), Jordi Roglans-Ribas (ANL)

Assessment of High Quality Plutonium-Fueled Core Configurations for the Versatile Test Reactor

Bo Feng, Florent Heidet (ANL)

Assessment of Low Enriched Uranium Fueled Core Configurations for the Versatile Test Reactor

Nicolas E. Stauff, Florent Heidet (ANL)

Preliminary In-Vessel Shielding Analysis for the Versatile Test Reactor

T. Fei (ANL), S. Bays (INL), F. Heidet (ANL)

Preliminary Control Rod Lifetime Assessment for the Versatile Test Reactor

Zhaopeng Zhong (ANL), Abdalla Abou-Jaoude (INL), Florent Heidet (ANL)

Preliminary Thermal-Hydraulic Assessment of the Versatile Test Reactor

Florent Heidet (ANL)

Evaluation of Pressure Drop for Possible Reflector Designs for the Versatile Test Reactor Using Nek5000

Dillon R. Shaver, Haomin Yuan, Florent Heidet (ANL)

Preliminary Evaluation of Fuel Management Strategies for the Versatile Test Reactor

Abdalla Abou-Jaoude, Sam Bays, Gilles Youinou (INL), Florent Heidet (ANL)

Fuel Loading Optimization and Planning for the Versatile Test Reactor

Michael Jarrett, Florent Heidet (ANL)

Versatile Test Reactor Preliminary Safety Analysis

Tyler Sumner, Tingzhou Fei, Nicolas Stauff, Thomas Fanning, Florent Heidet (ANL)

Probabilistic Risk Assessment Approach for the Versatile Test Reactor

David Grabaskas (ANL), Jason Andrus (INL), Dennis Henneke, Jonathan Li (GE-Hitachi), Matthew Bucknor, Acacia J. Brunett, Matthew Bucknor, Thomas Fanning (ANL)

Candidates for Non-Fuel Antineutrino Emissions in the High Flux Isotope Reactor

Andrew J. Conant, Anna Erickson (Georgia Tech)

Mesh and Effect on Thermal Hydraulic Calculations

Alok Jha (Homi Bhabha National Inst.), Anurag Gupta (Bhabha Atomic Research Centre)

Measurement of Reactor Kinetics Parameters in TREAT During Temperature Limited Transients

Thomas Holschuh, Daniel Wachs (INL)

Burnup Calculation Methodology for a Small-Scale Fuel Irradiation ?Experiment in the High Flux Isotope Reactor (HFIR)

J. R. Burns, C. M. Petrie, D. Chandler (ORNL)

Equilibrium Cycle Convergence During Predicted Bifurcation Using PARCS/PATHS for BWRs

P. Yarsky, A. Bielen (NRC)

Uncertainty Quantification/Reduction of BWR Core Characteristics Considering? Cross Section and Thermal-Hydraulics Uncertainties

Motohiro Ito, Akio Yamamoto, Tomohiro Endo (Nagoya Univ.), Tsuyoshi Ama (TEPCO)

A New Two-Step Framework with Improved Nodal Equivalence for PWR Depletion Analysis

Kyunghoon Lee (KAIST & KAERI), Woosong Kim (KAERI), Yonghee Kim (KAIST)

Real Variance Analysis of Unbiased Ratio Estimator in Monte Carlo k-Eigenvalue Calculation

HyeonTae Kim (KAIST), YuGwon Jo (KHNP-CRI), Yonghee Kim (KAIST)

Uncertainty Quantification of SMR Core Linear Power Using Polynomial Chaos Method

Syed Bahauddin Alam (FAEC, Rhode Island Nucl. Sci. Centre), Bader Almutairi (Missouri Univ. S&T, Kuwait Inst. Sci. Res.), Tuhfatur Ridwan (Cambridge), Dinesh Kumar (FAEC, Uppsala Univ.), Cameron S. Goodwin (Rhode Island Nucl. Sci. Centre)

Uncertainty Quantification on Core Input Parameter for SFR Core Using Polynomial Chaos

Syed Bahauddin Alam (FAEC, Rhode Island Nucl. Sci. Centre), Bader Almutairi (Missouri Univ. S&T, Kuwait Inst. Sci. Res.), Tuhfatur Ridwan (Cambridge), Denish Kumar (FAEC, Uppsala Univ.), Cameron S. Goodwin (Rhode Island Nucl. Sci. Centre)

Reactor Physics Analysis of Thorium-Based Fuel for Long-Life SMR Cores Using Seed-Blanket Fuel Concept

Bader Almutairi (Missouri S&T, Kuwait Inst. Sci. Res.), Dinesh Kumar (FAEC, Uppsala Univ.), Tuhfatur Ridwan (Cambridge), Syed Bahauddin Alam (FAEC, Rhode Island Nucl. Sci. Centre), Geoff Parks (Cambrige), Cameron S. Goodwin (Rhode Island Nucl. Sci. Centre), Shoaib Usman (Missouri S&T)

Performance Improvement of the Linear System Solver for CMFD Acceleration in PROTEUS-MOC

Yeon Sang Jung, Changho Lee (ANL)

3D SPN Transport and Diffusion Approaches for the Sodium-Cooled Fast Reactor Core Using Deterministic Method

Dinesh Kumar (FAEC, Uppsala Univ.), Bader Almutairi (Missouri S&T, Kuwait Inst. Sci. Res.), Tuhfatur Ridwan (Cambrige), Syed Bahauddin Alam (FAEC, Rhode Island Nucl. Sci. Centre), Cameron S. Goodwin (Rhode Island Nucl. Sci. Centre)

Investigating Simple Physical Means to Reduce TREAT Core Neutron Lifetime

John D. Bess, Thomas V. Holschuh II, Nicolas E. Woolstenhulme (INL)

Preliminary Neutronics Analysis for a Compact Heat-Pipe Cooled Fast Reactor Core

Qin Zeng, Yao Zhou, Ying Shi, Chenghao Li, Putong Wang (South China Univ.)

Operation of a Subcritical Reactor for Radioisotope Production

Faisal Y. Odeh, Alex C. Bakken, Amanda K. Grimm, Terry L. Grimm, Nathan C. Johnson, Christine M. Krizmanich, Mayir Mamtimin, William A. Peters, Kristin A. Shannon, Milan Stika, Robert N. Wahlen (Niowave)

Development of a Lead-Bismuth Cooled Subcritical Fast/Thermal Reactor

Mayir Mamtimin, Terry L. Grimm, Faisal Y. Odeh, William A. Peters, Robert N. Wahlen (Niowave), Puran Deng, Won-Sik Yang (Univ. Michigan), Stuart A. Maloy, Keith A. Woloshun (INL)

Implementation of Depletion Architecture in the MAMMOTH Reactor Physics Application

Olin Calvin (Univ. Florida), Javier Ortensi, Sebastian Schunert, Yaqi Wang, Mark DeHart (INL), Sedat Goluoglu (Univ. Florida)

Physics Assessment of Energy Deposition Distribution in Pressure-Tube Heavy Water Reactor Lattices with Uranium-Based and Thorium-Based Fuels

B. P. Bromley, J. Alexander, H. Yan, A.V. Colton, S. Golesorkhi (CNL)

Numerical Evaluation of the Pin-by-Pin Isotope Inventory Considering the Effects of Neutron Flux Level and Neutron Spectrum

Zafar Iqbal Zafar, Myung Hyun Kim (Kyung Hee Univ.)

TOPAZ-II and the HITEC: A Thermionic Reactor Design Comparison

Austin Lo, Jon Morell (U. C., Berkeley)

Activation Rates Validation to Support MSR Development

Evžen Losa, Michal Koš?ál, Jan Šimon (Research Centre ?ež), Ond?ej Chvála (U. T., Knoxville), Vlastimil Ju?í?ek (Research Centre ?ež)

Simulation of Thermal Spectrum MSR Using PROTEUS

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

Demonstration of the CFD Code Nek5000 for Molten Salt Applications

Dillon R. Shaver, Bo Feng, Elia Merzari, Florent Heidet (ANL)

Design Optimization and Burnup Analysis for Molten Chloride Fast Reactor

L.Y. He (Shanghai Inst. App. Phys.), G.C. Li (Tsinghua Univ.)

Chemical Overview of Molten Salts

Robin V. Roper (Univ. Idaho), Piyush Sabharwall (INL), Richard Christensen (Univ. Idaho)

A Versatile Experimental Salt Irradiation Loop (VESIL) in the Advanced Test Reactor

Abdalla Abou-Jaoude, Joe Palmer, James W. Sterbentz, Pattrick Calderoni (INL)

Design of a Small Modular Molten Salt Reactor

Lance Bullerwell (NCSU), Nicholas Smith (Southern Co.), Jason Hou (NCSU)

MPACT Linear Source MOC Validation with Pin Resolved and Temperature Varying Measurements

Kyle Vaughn, Brendan Kochunas, Ethan Cole, Thomas Downar (Univ. Michigan)

A Demonstration of BWR Coupled Analysis and Potential ATF Applications Using CASL’s MPACT/CTF

Jacob P. Gorton (U. T., Knoxville, ORNL), Benjamin S. Collins (ORNL), Nicholas R. Brown (U. T., Knoxville)

Achieving High-Power Configuration in Missouri S&T Reactor (MSTR) for Potential Uprate

Thaqal Alhuzaymi (King Abdulaziz City, Missouri Univ. S&T), Ayodeji B. Alajo (Missouri Univ. S&T)

Low-Power Core Reconfiguration for Missouri S&T Reactor (MSTR)

Thaqal Alhuzaymi (King Abdulaziz City, Missouri Univ. S&T), Ayodeji B. Alajo (Missouri Univ. S&T)

A Zero-Power Hybrid Fast and Thermal Subcritical Testbed

P. Deng, W. S. Yang (Univ. Michigan), F. Y. Odeh, M. Mamtimin (Niowave)

Revisiting Saxton Plutonium Project MOX Fuel Experiments as International Benchmarks

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

SPERT III E-Core Critical Experiments Calculation with NECP-X

Chen Zhao, Zhouyu Liu (Xi'an Jiaotong Univ.), Thomas Downar (Univ. Michigan), Liangzhi Cao (Xi'an Jiaotong Univ.)

Simulation of Spherical Fast Burst Reactor Pulses Using MCATK

Scott Dossa (Univ. Minn.), Travis J. Trahan (LANL)

Utilization of the Precursor-Based Delayed Neutrons Emission Model for a Control Rod Insertion Transient

A. Talamo, Y. Gohar (ANL), S. Sikorin, S. Mandzik, S. Polazau, T. Hryharovich (Joint Inst. Power and Nucl. Res.), V. Valtavirta, J. Leppänen (VTT)

Comparison of the Reactivity Feedback Effects Between a Molybdenum-Producing ?PHWR Fuel Bundle and a Standard PHWR Fuel Bundle

Jawad Haroon, Eleodor Nichita (Ontario Inst. Technol.)

Overview of Nuclear Data Needs for Nuclear Energy Applications

B. T. Rearden, F. Bostelmann, V. Sobes, A. M. Holcomb (ORNL)

Turbulent Flow Measurements of the Under-Expanded Free Jet and Jet Impinging on a Flat Surface

B. Maher, T. D. Nguyen, C. F. Matozinhos, G. C. Q. Tomaz, Y. A. Hassan (Texas A&M)

Temperature Measurements in Sub-cooled Boiling Using Laser Induced Fluoresce Technique (LIF)

Bandar Alkhudhiri, Yassin A. Hassan (Texas A&M)

Temperature Measurement of Direct Contact Condensation of Steam Using Backlight Aided LIF

Joseph Seo, Sero Yang, Yassin A. Hassan (Texas A&M)

Facility for Simulating Transient Boiling Behavior Under PWR Conditions

C. Jensen, C. Folsom, N. Woolstenhulme, N. Smith, K. Condie (INL), K. Terrill, R. Christensen (Univ. Idaho)

Experimental Research of Jet Diameter on Heat Transfer in a Small Steel Containment

Shengfei Wang (North China Electric Power Univ.), Yusheng Liu (Nuclear and Radiation Safety Center), Xiaowei Jiang (Nuclear Power Inst.)

An Investigation to Develop Measurement Techniques for Quantifying Fission Product Transport in a Gas-cooled Fast Reactor—Versatile Test Reactor Program

D. Orea, B. H. Choi, D. T. Nguyen, R. Vaghetto, N. K. Anand, Y. A. Hassan (Texas A&M), Piyush Sabharwall (INL)

Experimental Study on Non-Condensable Gas Effect on Heat Transfer ?Coefficient in Steam/Air Direct Contact Condensation

Joseph Seo, Sero Yang, Kimoon Lee, Yassin Hassan (Texas A&M)

Assessment of Potential Improvements in Level II PRAs for Advanced ?Reactors based on Improved Aerosol Removal Mechanisms

Rohan Biwalkar, Sola Talabi (Pittsburgh Technical), Kenneth Redus (Redus and Assoc.)

Numerical Simulation and Experimental Study on Natural Vibration Characteristics ?of Heat Exchanger in a LMFBR Intermediate Heat Exchanger

Mengmeng Liu, Guangdong Song (China Inst. Atomic Energy)

Numerical Investigation of Flow in Rod Bundle Subchannels on Natural Convection: Effect of Twisted Tapes

Salman Alzahrani (King Abdulaziz City, Missouri Univ. S&T), Shoaib Usman (Missouri Univ. S&T)

S-RELAP5 and RELAP5/MOD2-B&W Validation for Long Term Core Cooling Following a Large-Break LOCA

C. K. Nithianandan, Andrei Burghelea, Kent Abel, Robert L. Baxter Jr., Gordon Wissinger, John Klingenfus (Framatome)

Preliminary Heater Rod Design for Transient Critical Heat Flux Experiments in TREAT

Richard Hernandez (Penn State), Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen (INL), Nicholas R. Brown (U. T., Knoxville)

Point Kinetics and Reactivity Feedback Modeling in SAM

Guojun Hu, Guanheng Zhang, Rui Hu (ANL), Joseph M. Kelly (NRC)

Effect of Off-Nominal Channel Thickness for MITR LEU Conversion

Dakota Allen, Akshay J. Dave, Kaichao Sun, Lin-Wen Hu (MIT), Son H. Pham, David Jaluvka, Erik H. Wilson (ANL)

RCIC Terry Turbine Nozzle Simulation with RELAP5-3D

Hongbin Zhang, Tyler Hughes (INL)

Study of Vortex Shedding in Helical Coil Steam Generator

Mustafa Alper Yildiz (Texas A&M), Elia Merzari (ANL), Yassin Hassan, Marilyn Delgado (Texas A&M)

Recent Advances in the Coupling of SAS4A/SASSYS-1 and ?STAR-CCM+ for Sodium-Cooled Fast Reactor Transient Analyses

Adam Kraus, Acacia Brunett (ANL)

Numerical Study on the Thermal Stratification Phenomenon in the Sodium-Cooled Fast Reactor

Dalin Zhang, Shibao Wang, Suizheng Qiu, Guanghui Su (Xi'an Jiaotong Univ.)

Numerical Investigation on the Hemispherical Downward Facing Pool Boiling of a Simulated Reactor Vessel

Xiang Zhang, Daogui Tian, Bin Jiang, Lian Chen (SNPTC)

Uncertainty Assessment for Small Break LOCA of a Generation III Reactor

Ye Yang, Jun Yang, Chengcheng Deng

The Application of Dual-Mesh Coupled Heat Transfer Porous Media Model on the Numerical Simulation of a Shell-Tube Heat Exchanger

Guangdong Song (China Inst. Atomic Energy), Qingchuan Yang (Xi'an Jiaotong Univ.), Hongyi Yang (China Inst. Atomic Energy), Binbin Qiu (Xi'an Jiaotong Univ.), Huajin Yu, Mengmeng Liu (China Inst. Atomic Energy)

Preliminary TH Analysis on Steam Generator Tube Rupture Without High Pressure Safety Injection

Jisuk Kim, Man Cheol Kim (Chung-Ang Univ.)

Critical Heat Flux Study with Different Substrate Conditions for Accident Tolerant Fuel Cladding Development

HangJin Jo, Emilio Gutierrez, Hwasung Yeom, Kumar Sridharan, Michael Corradini (U. W., Madison)

Thermal Hydraulic Performances Analysis of Cr-Coated Zircaloy Clad During Station Blackout Accident

Jun Wang, Hwasung Yeom, Michael Corradini (U. W., Madison)

Sensitivity of Critical Heat Flux for ATF FeCrAl Alloy Using RELAP5-3D and RAVEN

Jacob P. Gorton (U. T., Knoxville, Penn State), Nicholas R. Brown (U. T., Knoxville)

Potential Impact of Increased Critical Heat Flux for FeCrAl Clad Fuels in Hot Zero-Power Rod-Ejection Accidents

Robert F. Kile(U. T., Knoxville, Penn State), Nicholas R. Brown (U. T., Knoxville)

Scaling Methodologies for SET and IET–Panel

Lane Carasik (USNC - Space)

Bubble Formation Through Submerged Vertical Orifices with Horizontal Air Inflow

Naveen Pillai, Katharina Stapelmann, Igor A. Bolotnov (NCSU)

Investigation on Bubble Deformation and Break-Up Dynamics Using Interface Tracking Method

Yuqiao Fan, Igor Bolotnov (NCSU)

Large Eddy Simulation of the Turbulent Flow Around a Helical Coil Steam Generator Geometry for a Small Modular Reactor

Samuel J. Lee, Yassin A. Hassan (Texas A&M)

Steady State Predictions of Reflood Characteristics in a Rod Bundle

Grant R. Garrett, Yue Jin, Faith R. Beck, Fan-Bill Cheung (Penn State), Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie (NRC)

Effect of Fouling on Quenching of Simulated Fuel Rods

Faith R. Beck, Yue Jin, Grant Garrett, Fan-Bill Cheung (Penn State), Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie (NRC)

Effect of Thermal Effusivity on Nanoparticle Deposited Surface CHF

Ji Yong Kim, In Cheol Bang (UNIST)

The Statistical Analyses on the Bubble Contact Diameters in the Vertical Narrow Channel

Qi Lu, Yu Liu, Wei Liu, Xi Chen, Hangxing He, Linglan Zhou (Nuclear Power Inst. China)

Injectable Sacrificial Material Safety System to Mitigate Molten Corium in Containment

David L. Y. Louie, Yifeng Wang, Rekha Rao, Alec Kucala, Jessica Kruichak, William Chavez (Sandia)

Experimental Investigation on Ex-Vessel Debris Bed Formation Using Simulant Particles

Sang Mo An, Sang Ho Kim, Jin Ho Park (KAERI)

Development of Simplified Ex-Vessel Debris Bed Coolability Model

Jaehoon Jung, Sang Mo An, Sang Ho Kim (KAERI)

Calculation and Study on DCP of Hydrogen Igniter Design in PWR with Large Containment

Ding Chao (Tsinghua Univ.), Yang Zhiyi, Chai Guohan (Nuclear Radiation Saftey Center), Zhou Zhiwei (Tsinghua Univ.)

Effect of Subcooling on Flow Boiling CHF Using a Full Scale 2-D Curved Test Section for ERVC

Xiang Zhang, Daogui Tian, Bin Jiang, Lian Chen (SNPTC)

Analysis of Core Coolability During a Severe Accident with Delayed External Injection for CPR1000

Zhi’ao Huang, Huifang Miao, Huai-En Hsieh, Ning Li (Xiamen Univ.)

A Zero-Dimensional Model for Dryout Heat Flux of Debris Bed Considering Interfacial Friction Between Two Phases

Dong Yeol Yeo, Hee Cheon No (KAIST)

Analysis of PWR SBO Scenarios Under Refueling Condition Using MAAP5

Peng Yuan, Xiaoli Wu (Nuclear Power Inst. China)

Thermal Analysis for SRS Saltstone Disposal Facility

Enrique Molina (U. T., Rio Grande), Si Y. Lee (SRNL)

Thermal-Hydraulic Design of Visual 3D Printed Integral Test Facility Toward Nuclear Innovation Platform

Kyung Mo Kim, Ji Hyun Kim, In Cheol Bang (UNIST)

Optimization of Airfoil PCHE for the Recuperator of Nitrogen Brayton Cycle

Jin Gyu Kwon, Joo Hyun Park, Tae Ho Kim, Moo Hwan Kim (POSTECH)

Development of Regulatory Audit Framework for Asymmetric Events of the Non-LOCA

Il Suk Lee (KINS, Korea Univ.), Dong H. Yoon, Tae H. Kim, Ahn D. Shin (KINS), Yong C. Kim (Korea Univ.)

Pitch Your PhD–Panel

Nicolas E. Stauff (ANL)

Creating a Successful Career–Panel

Kelsey Amundson (U. C., Berkeley)

Innovations in Nuclear Education–Panel

Matthew Jeffrey Jasica (Sandia)

Advanced Nuclear NOW! Showcasing Technology Near Deployment–Panel

Abdalla Abou-Jaoude (INL)

From Nuclear Advocacy to Policy, From Local to Global–Panel

Fidelma Giulia Di Lemma (INL)