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Table of Contents

SPECIAL SESSIONS

BIOLOGY AND MEDICINE

Biology and Medicine: General

9

Parametric Study of X-ray Energy Modulation for Depth Sensitive Backscatter Imaging

11

  • Lucas M. Rolison, Kelly A. Jordan, Sanjiv S. Samant (Univ. Florida)

Electron Beam Cherenkov Emission Measurements for Quality Assurance

15

  • William Chuirazzi, Richard Shawger, Ahmet S. Ayan, Jeffrey Woollard, Nilendu Gupta, Lei Caoa (Ohio State)

Demonstration of a Correlation between Tumor Absorbed Dose and Response in Several Pediatric Tumor Xenografts Treated with Radioiodinated CLR1404 Alkyl-Phospholipid Ether

19

  • Bryan Bednarz, Ian Marsh, Dana C. Baiu, Alexander E. Boruch, Ankita Shahi De, Saswati Bhattacharya, Justin Jeffery, Qianqian Zhao, Lance Hall, Jamey Weichert, Mario Otto (Univ. Wisconsin, Madison)

DECOMMISSIONING AND ENVIRONMENTAL SCIENCES

Korean Decommissioning and Environmental Remediation for Korean Reactors

25

Consideration for Implementing the Safety Regulation Plans on Permanent Shut-Down NPP during Transition Period in Korea

27

  • Yong Ki Chi, Kyungwoo Choi, (Korea Institute of Nuclear Safety)

Preliminary Dose Assessment during Dismantling Biological Shield of Kori Unit-1

29

  • Choong Wie Lee, Choong Wie Lee, HyungJun Kim, Donghyun Lee, Hee Reyoung Kim (UNIST)

Preliminary Evaluation of Decontamination Agent and Ion Exchange Resin Requirements for System Decontamination of a Nuclear Power Plant

31

  • HakSoo Kim, Doo-Ho Lee, Deok-Ki Kim, Cho-Rong Kim (Korea Hydro & Nuclear Power Co.)

Regulatory Consideration on Decommissioning Facilitation of Nuclear Power Plants in Korea

33

  • Kyung-woo Choi, Byung-il Kim (Korea Institute of Nuclear Safety)

A New Graphical Dismantling Process Simulation Technology for Flexible Planning of Nuclear Facility

35

  • Byung-Seon Choi, Dongjun Hyun, Ikjune Kim, Jonghwan Lee,  Jeikwon Moon (KAERI)

Chemical Decontamination Performance of Radioactive Metal Surface Using HyBRID Process

38

  • Wangkyu Choi, Seonbyeong Kim, Sangyoon Park, Huijun Won, Jeikwon Moon (KAERI)

Optimal Energy Strategies Aimed at Sustainable Reduction of Greenhouse Gas Emissions – Panel—I

41

Optimal Energy Strategies Aimed at Sustainable Reduction of Greenhouse Gas Emissions – Panel—II

43

Environmental Challenges and Lessons Learned from Decommissioning Nuclear Facilities in California – Panel

45

EDUCATION, TRAINING, AND WORKFORCE DEVELOPMENT

Focus on Communications: Telling the Nuclear Story Through Digital and Social Media–Panel—I

49

Focus on Communications: Building Strong Networks for Clean Energy Advocacy–Panel—II

51

FUEL CYCLE AND WASTE MANAGEMENT

Backend of the Fuel Cycle for Small Modular Reactors–Panel

55

Recycle and Reuse of Used Nuclear Fuel Resources

57

Engineering Scale Development/Demonstration of Zirconium Recovery from Used Fuel Cladding

59

  • E. D. Collins, G. D. DelCul, J. A. Johnson, T. D. Hylton, R. D. Hunt, B. B. Spencer, E. C. Bradley (ORNL)

Characterization of the Chlorination Products of Zirconium Alloys used for Nuclear Fuel Cladding

63

  • Rosendo Borjas Nevarez (Univ. of Nevada, Las Vegas)

Purification of Zirconium Tetrachloride (ZrCl4) from UNF Cladding - A Progress Report

67

  • Craig Barnes, (Univ. Tenn), Guillermo (Bill) Daniel DelCul (ORNL), David F. McLaughlin (Westinghouse), Michael Orick, Ales Styskalik (Univ. Tenn)

Computational Studies of Gas Phase Reactions of Zirconium Tetrachloride (ZrCl4) and Metal Chloride Impurities

68

  • Michael Orick, Ales Styskalik (Univ. Tenn.), Guillermo (Bill) Daniel DelCul (ORNL), David F. McLaughlin (Westinghouse), Craig Barnes (Univ. Tenn.)

Adsorption of Chlorine on Zr(0001) Surface: First-Principles Predictions

69

  • Eunja Kim (Univ. Nevada, Las Vegas), Philippe F. Weck (SNL), Rosendo Borjas, Frederic Poineau (Univ. Nevada, Las Vegas)

Removal of Tritium from the Gaseous Effluents Produced by the Recovery of Zirconium from Used Fuel Cladding

72

  • S. H. Bruffey, B. B. Spencer, G. D. DelCul (ORNL)

Tritium Management Requirements and Approaches for UNF Reprocessing

76

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

Modulation of Tetravalent Actinide Oxalate Morphology through Organic Compounds

78

  • Blaise Haidon, Benedicte Arab-Chapelet (CEA Marcoule), Pascal Roussel (UCCS-UMR), Thibaud Delahaye, Murielle Bertrand (CEA Marcoule), Stephane Grandjean (CEA), Murielle Rivenet (UCCS-UMR)

Long-Term Once-Through Fuel Cycles-From Seawater Uranium to Breed and Burn

83

Uranium from Seawater Cost Analysis: Recent Updates

85

  • Margaret Flicker Byers, Erich Schneider (Univ. Texas, Austin)

Cost Analysis of Wind and Uranium from Seawater Acquisition symBiotic Infrastructure using Shell Enclosures

89

  • Maha N. Haji (MIT), Margaret E. Flicker Byers, Erich A. Schneider (Univ. Texas, Austin), Alexander H. Slocum (MIT)

Use of NAA to Detect Uptake of Uranium and other Elements in Adsorbents

93

  • Sebastian Eder, Margaret Byers, Erich Schneider (University of Texas at Austin)

Assessment of Near-Breeding Heterogeneous Seed/Blanket Cores in Pressure-Tube Heavy Water Reactors with Thorium-Based Fuels

97

  • A. V. Colton, B. P. Bromley, S. Golesorkhi (Canadian Nuclear Laboratories)

Waste Management, Ethics, and Resilience—Professor Joonhong Ahn's Legacy

103

Integrated Modeling and Monitoring Technologies for Environmental Resiliency in Nuclear Energy

105

  • Haruko M. Wainwright (LBNL), Franziska Schmidt (Univ. California, Berkeley), Boris Faybishenko (LBNL)

Used Nuclear Fuel Management in Asia

107

  • Jor-Shan Choi (Univ. California, Berkeley)

The Criticality Safety Studies of Joonhong Ahn

110

  • Alex Salazar, Milos Atz, Xudong Liu, Massimiliano Fratoni (Univ. California, Berkeley)

Effect of Socio-Political Factors  in Nuclear Power Development in Multi-National Framework

114

  • Viet Phuong Nguyen, Man-Sung Yim (Korea Adv. Institute of Science & Tech)

Innovation Opportunities in Future Fuel Cycles–Panel

117

University Research in Fuel Cycle and Waste Management—I

119

A New Group Crystallization Approach in Used Nuclear Fuel Recycling: A Look at Fission Product Behaviors

121

  • Andrew J. Wilcox (Texas A&M Univ.), Bruce A. Moyer (ORNL), Jonathan D. Burns (Texas A&M Univ.)

Elevated Temperature Alpha Spectroscopy with Nickel-Platinum 4H-SiC Schottky Diodes

123

  • Joshua Jarrell, Eric Moore, Thomas Blue, Lei Cao (Ohio State)

Chabazite Zeolite Membranes for Krypton/Xenon Separation: Control of Membrane Properties and Process Modeling

126

  • Yeon Hye Kwon, Byunghyun Min, Christine Kiang (Georgia Tech.), Ramesh Bhave (ORNL), Sankar Nair (Georgia Tech.)

Aging Processes of Silver Mordenite and Silver Functionalized Aerogel in Dry Air, Humid Air, and NO/N2

130

  • Yue Nan, Seungrag Choi (Syracuse Univ.), Austin Ladshaw, Sotira Yiacoumi (Georgia Tech.), Costas Tsouris (Georgia Tech/ORNL), David DePaoli (ORNL), Lawrence L. Tavlarides (Syracuse Univ.)

Effect of Moisture on the Adsorption of Iodine and Krypton in Multicomponent Streams on the 10 WT% C/ETS-10 Sorbent

133

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

Nuclear Fuel Cycle Simulator as a Means to Model a Nuclear Hybrid Energy System

136

  • Emma K. Redfoot, R. A. Borrelli (Univ. Idaho)

Energy Conversion Loop: Process Heat Applications of Hybrid Energy System

140

  • Kelley M. Verner, Lee T. Ostrom (Univ. Idaho), Michael G. McKellar (INL)

University Research in Fuel Cycle and Waste Management—II

145

Effects of GdCl3 on U Electrochemical Properties in LiCl-KCl-UCl3-GdCl3 Salt

147

  • Dalsung Yoon, Supathorn Phongikaroon (Virginia Commonwealth Univ.)

Electrochemical and Thermodynamic Properties of U in LiCl-KCl-UCl3 Salt System

151

  • Dalsung Yoon, Supathorn Phongikaroon (Virginia Commonwealth Univ.)

Electrochemical Behavior of Lanthanum in Molten LiF-NaF-KF “Flinak” Eutectic Salt

155

  • Ryan Chesser, Shaoqiang Guo, Jinsuo Zhang (Virginia Tech Univ.)

Electrochemical Study of BaCl2 and CsCl on a Liquid Bismuth Cathode in LiCl-KCl Eutectic Salt

158

  • Michael Woods, Supathorn Phongikaroon (Virginia Commonwealth Univ.)

Development of a Small Liquid Sodium Purification Loop

162

  • James Schneider, William K. Nollet (Fort Lewis College)

Ion Exchange of LiCl-KCl in H-Y Zeolite for Dechlorination of Electrorefiner Salt Waste Forms

165

  • Manish Wasnik, Krista Carlson, Michael Simpson (Univ. Utah)

Normal Pulse Voltammetry for Real Time Analysis of Electrorefiner Salt with High Concentrations of Analytes

167

  • Chao Zhang, Michael F. Simpson (Univ. Utah)

Electrochemical Separation for Used Nuclear Fuels

169

Separation of Actinides from Lanthanides in Molten Fluorides by the Modulated-Current Electrolysis

171

  • Martin Straka, Lorant Szatmary (UJV Rez, a.s.)

Nuclear Material Monitoring in Molten Salt Systems using Cyclic Voltammetry

174

  • Vickram Singh, Dev Chidambaram (Univ. Nevada, Reno)

Electrochemical Sensor Development for Fluoride Molten Salt Redox Control

176

  • Nikolas Shay, Shaoqiang Guo, Jinsuo Zhang (Ohio St.Univ.)

First-Principles-Based Computational Study on Nucleation and Growth Mechanisms of U on Mo(110) Surface Solvated in an Eutectic LiCl-KCl Molten Salt

178

  • Choah Kwon, Joonhee Kang, Byungchan Han (Yonsei Univ.)

Effect of Concentration, Temperature, and Interelectrode Gap on Voltage Drop in Electrochemical System of GdCl3-LiCl-KCl

182

  • Hunter Andrews, Supathorn Phongikaroon (Virginia Commonwealth Univ.)

Fuel Cycle and Waste Management: General—I

185

Economic Module Development for the Fuel Cycle Simulation Tool CLASS

187

  • Federico Casella (Institut Polytechnique de Grenoble & Instituto Balseiro/Centro Atómico Bariloche), Adrien Bidaud (Institut Polytechnique de Grenoble), Nicolas Thiollière (CNRS Univ.)

Exploring the Use of Muon Momentum for Detection of Nuclear Material Within Shielded Spent Nuclear Fuel Dry Casks

190

  • S. Chatzidakis, P. A. Hausladen, S. Croft, J. A. Chapman, J. J. Jarrell, J. M. Scaglione (ORNL), C. K. Choi, L. H. Tsoukalas (Purdue Univ.)

On the Use of Ionic Liquids for the Recycling of the Contaminated Material

194

  • Martin Straka (UJV Rez, a.s.)

Preliminary Analysis of Facility Design for Pyroprocessing Safeguardability

197

  • R. A. Borrelli, Malachi Tolman, Jieun Lee (Univ. Idaho)

Major Considerations on the Nuclear Material Accounting of PB-HTR Commercial Plants

201

  • Bing XIA, Ding SHE, Chunlin WEI, Jiong GUO, Jian ZHANG, Fu LI, Liguo ZHANG, Zaizhe YIN (Tsinghua Univ.)

Fuel Cycle and Waste Management: General—II

205

Conceptual Design of Decontamination System for Radioactive Contaminated Water with Microalgae

207

  • Dohyung Kim, Wooyong Kim, Unjang Lee (ORION ENC Co. Ltd.), Seung-Yop Lee (Sogang Univ.)

Sorption of Cobalt from Aqueous Solutions by Polystyrene-Graphene Oxide Composite Material

209

  • Zdeňka Tomášová, Mária Bubeníková (UJV Rez, a.s.), Petra Ecorchard (Institute of Inorganic Chemistry of the AS CR)

Initial Shipment of MNSR Reactor HEU Spent Nuclear Fuel from Ghana to China

212

  • John Dewes (SRNL), Kwame Aboh, Henry Odoi (National Nuclear Research Inst.), Igor Bolshinsky (INL), Sándor Tózsér (IAEA)

Chemical Consequence Analysis and Atmospheric Dispersion Coefficients under DOE-STD-3009-2014 Nuclear Safety Analysis

218

  • Roger D. Lanning (Bechtel Inc.)

Integrated Used Fuel Storage Sites

223

SNF Data Visualization on the Centralized Used Fuel Resource for Information Exchange (CURIE) Website

225

  • Robert Anthony Joseph, Aaron Myers, Joshua Jarrell, Joshua Peterson, Kaushik Banerjee (ORNL)

Estimating Public Dose Along Hypothetical Spent Nuclear Fuel Transportation Routes

229

  • Kevin J. Connolly (ORNL)

Experimental Evaluation of an Oxidizing Hazard in the Presence of Sorbents

233

  • J. F. Lucchini, B. A. Crawford, C. J. Chancellor, C. Poulos, T. Hayes (LANL)

Should WIPP Resume Unfiltered Discharge of Underground Ventilation?

235

  • P. Thakur, H. Khaing, R. Hardy (Carlsbad Environmental Monitoring & Research Center)

FUSION ENERGY

Neutronics Challenges of Fusion Facilities—I

241

Simulation of the Prompt Dose Environment in the NIF during High Yield Shots

243

  • Hesham Y. Khater, Sandra Brereton (LLNL)

Overview of Nuclear Integration Activities for Mitigation of Radiation Loads to ITER Superconducting Magnets

247

  • Raul Pampin, Dieter Leichtle, Marco Fabbri (Fusion for Energy), Rafael Juarez, Aljaz Kolsek (UNED),  Michael Loughlin, Neil Mitchell, Eduard Polunovskiy (ITER), Shanliang Zheng (CCFE)

Investigations into Alternative Radiation Transport Codes for ITER Neutronics Analysis

251

  • Andrew Turner (UK Atomic Energy Authority)

Development of the Advanced D1S for Shutdown Dose Rate Calculations in Fusion Reactors

255

  • Rosaria Villari, Davide Flammini, Fabio Moro (ENEA), Luigino Petrizzi (European Commission)

Development of Fusion Neutronics Methodology, Software, and Testing Facility in FDS Team

259

  • Yican Wu, Jing Song, Pengcheng Long, Liqin Hu, Chao Liu, FDS Team (Inst. Nuclear Energy Safety Tech., Chinese Academy of Sciences)

Neutronics Challenges of Fusion Facilities—II

261

Integration of the ITER Tokamak C-model with the Building Model

263

  • Jinan Yang, Stephen C. Wilson, Scott W. Mosher (ORNL)

Calculation of Activated Water Radiation Maps in ITER

265

  • Shrichand Jakhar, Michael Loughlin (ITER Organization)

How to Reduce Shutdown Dose Rates in ITER Diagnostics Equatorial Ports

268

  • R. Juarez (UNED), J. Guirao (ITER Organization), A. Kolsek (UNED), M. Kochergin (Fircroft Engineering Services Ltd.), G. Pedroche, A. J. López-Revelles (UNED), V. Udintsev, L. Bertalot (ITER Organization), M. Ivantsky (Budker Inst. of Nuclear Physics), A. Zonkov, A. Alexandrov (Project Center ITER), J. Sanz (UNED), M. Walsh (ITER Organization)

ITER Neutronic Challenges for Upper Port 14

272

  • Jonathan P. Klabacha, Brian C Linn, Russell E. Feder (PPPL)

Neutronics Analysis for ITER Diagnostic Generic Upper Port Plug

275

  • A. Serikov (KIT), L. Bertalot (ITER Organization), U. Fischer (KIT), R. Juarez (ETSII-UNED), M. Walsh (ITER Organization)

Fusion Energy Applications

279

Study of Tritium Transport in Nuclear Grade Graphite and Molten Fluoride Salt Systems

281

  • Huali Wu, Ruchi Gakhar (Univ. Wisconsin, Madison), Cristian Contescu (ORNL), Raluca O. Scarlat (Univ. Wisconsin, Madison)

Tersoff Benchmarking of Be-C-H Interatomic Potential

285

  • Aws Al-Shalash, Abdullah Weiss, Xue Yang (Texas A&M Univ., Kingsville)

Theoretical Calculation and Simulation Studies of Balancing Forces and Axisymmetric Poloidal Halo Current in EAST

287

  • Shahab Ud-Din Khan (COMSATS/CAS), Salah Ud-Din Khan (King Saud Univ.), Farooq Ahmed Shah, Kainaat Ashraf, Sehrish Bibi, Rubab Gull (COMSATS)

HUMAN FACTORS, INSTRUMENTATION, AND CONTROLS

Human Factors, Instrumentation and Controls: General—I

293

Determination of a Generic Human Error Probability Distribution, Part 1: A Dynamic Formulation of SPAR-H

295

  • Sarah M. Ewing, Kateryna Savchenko, Diego Mandelli, Ronald Boring (INL)

Determination of a Generic Human Error Probability Distribution, Part 2: A Dynamic SPAR-H Example Application

299

  • Sarah M. Ewing, Ronald Boring, Diego Mandelli, Kateryna Savchenko (INL)

Development of Performance Validation Tool for the NPCS for APR1400

303

  • See Chae Jeong, In Ho Song, Gyu Cheon Lee (KEPCO E&C), Ha Young Lim, Mun O Heo (KHNP)

Nuclear Power Plant Control Room Modernization - Simulation Based Design

306

  • Bruce Hallbert, Bahram Meyssami, Sean Fuller (INL)

Feasibility of Applying a Human Bio-Signals Monitoring System to Minimize Insider Threats

307

  • Young A. Suh, Man-Sung Yim (KAIST)

Human Factors, Instrumentation and Controls: General—II

311

Cybersecurity Vulnerability Assessment Methodologies for Nuclear Power Plants

313

  • John Peterson​, Michael Haney, R. A. Borrelli (Univ. Idaho)

Introduction of Diverse Manual Actuation Design for APR1400

317

  • Wonwook Kim, Byung-Soo Cho, Ki-hyung Kim, Jong-Jae Choi (KEPCO E&C)

Examining Two-Phase Flow with Optical Sensors

321

  • James Schneider (Fort Lewis College), Darius D. Lisowski (ANL)

Increasing ROI Using Your Digital Twin for Model Based Engineering

325

  • Scott Zepplin (GSE Performance Solutions Inc.)

ISOTOPES AND RADIATION

Isotopes and Radiation: General

329

Investigation of Scintillator Based Partial Defect Detector for Safeguarding Spent Fuel Assemblies

331

  • Haneol Lee, Man-Sung Yim (KAIST)

Preprocessing Analysis of the Multi Isotope Process Monitor

334

  • Nathan Gilliam, Jamie Coble (Univ. Tenn., Knoxville), David Meier (PNNL)

Developing a GUM Compliant Uncertainty Approach for NDA Gamma Analysis Using FRAM

338

  • Jung H. Rim, Donivan R. Porterfield (LANL), Michael D. Yoho (Univ. Texas, Austin)

Resonance Self-Shielding Impact on Neutron Spectrum Determination for Missouri S&T Reactor

340

  • Meshari AL Qahtani, Ayodeji B. Alajo (Missouri Univ. of Sci. and Technol., Rolla)

Helicon-Injected Inertial Electrostatic Confinement Neutron Source or Space Propulsion Device

343

  • George H. Miley, Drew Ahern (Univ. Illinois, Champaign-Urbana)

MATERIALS SCIENCE AND TECHNOLOGY

Nuclear Science User Facilities: Fuels Work—I

347

Microanalysis of Irradiated Metallic Hydride Nuclear fuel (U0.17 ZrH1.6) Fuels

349

  • Michele Conroy, Edgar C. Buck (PNNL), Mehdi Balooch (Univ. California, Berkeley), Andrew M. Casella (PNNL)

The Characterization of Microstructure and Chemistry of Transmutation Fuels

352

  • Assel Aitkaliyeva (INL/Univ. Florida), Cynthia A. Papesch (INL)

Hydride Microstructure at the Metal-Oxide Interface of a Zircaloy-4 Fuel Clad from the H. B. Robinson Nuclear Reactor

354

  • M. Nedim Cinbiz, Philip D. Edmondson, Kurt Terrani (ORNL)

Fission Product and Actinide Distribution in the Sic Layer of Fissioned Triso Fuel Particles

357

  • Rachel L. Seibert (IIT), Tyler J. Gerczak, J. Hunn, C. Baldwin, F. Montgomery, K. Leonard, L. Terrani (ORNL), Jeff Terry (IIT)

Microstructure Investigations of U3Si2 Irradiated by Heavy Ions at LWR Temperatures

359

  • Yinbin Miao (ANL), Jason Harp (INL), Kun Mo (ANL), Sumit Bhattacharya (Northwestern Univ.), Abdellatif M. Yacout (ANL)

Microstructural Characterization of Irradiated U0.17ZrH1.6 Using Ultrasonic Techniques

361

  • Pradeep Ramuhalli, Richard Jacob, Paul J. MacFarlan, Andrew M. Casella (PNNL)

Nuclear Science User Facilities: Ion Beam and NSUF Capabilities —II

365

Application of NSUF Capabilities Towards Understanding the Emulation of  High Dose Neutron Irradiations with Ion Beams

367

  • K. G. Field (ORNL), S. Taller (Univ. Michigan), C. J. Ulmer (Penn State), Z. Jiao (Univ. Michigan), T. A. Saleh (LANL), A. T. Motta (Penn State), G. S. Was (Univ. Michigan)

Neutron and Ion Irradiation Studies on Advanced Steels Using the Nuclear Science User Facilities

369

  • Xiang Liu (Univ. Illinois, Urbana-Champaign), Yinbin Miao, Wei-Ying Chen (ANL), Yaqiao Wu (Boise State), Meimei Li (ANL), James F. Stubbins (Univ. Illinois, Urbana-Champaign)

Microstructural Evolution of NF709 Steel under In-situ Ion Irradiations at Room Temperature to 600 °C

371

  • Chi Xu (Univ. Florida & ANL), Meimei Li, Mark Kirk, Peter Baldo (ANL), Yong Yang (Univ. Florida)

Materials Characterization using the Center for Synchrotron Radiation Research and Instrumentation (CSRRI), a NSUF Partner Facility

373

  • Rachel Seibert, Daniel Velazquez, Zhengrong Lee, Jeff Terry (IIT)

In Situ Experimental Capabilities and Results from the X-ray Powder Diffraction Beamline

375

  • David J. Sprouster, Mohamed S. Elbakhshwan, S. K. Gill, Lynne E. Ecker (BNL)

Nuclear Science User Facilities Irradiation Capabilities at Oak Ridge National Laboratory

377

  • Christian Petrie, Joel McDuffee, Nesrin Cetiner, Richard Howard, Padhraic Mulligan (ORNL)

Nuclear Science User Facilities: Structural Materials—III

381

Microstructure of In-Core Molten Salt Corrosion Hastelloy N® and 316 Stainless Steel

383

  • G. Zheng, D. Carpenter, M. Ames, G. Kohse, L. Hu (MIT)

Post Irradiation Examination of SiC Tube Subjected to Simultaneous Irradiation and Radial High Heat Flux

386

  • Takaaki Koyanagi, Yutai Katoh, Christian M. Petrie, (ORNL), Christian P. Deck (General Atomics), Kurt A. Terrani (ORNL)

Correlation Between Irradiation Defects and Transition Dimension for TEM In Situ Mechanical Testing

389

  • Kayla H. Yano (Boise St. Univ.), Priyam V. Patki (Purdue Univ.), Matthew J. Swenson (Boise St. Univ.), Janelle P. Wharry (Purdue Univ.)

Irradiation Response of the Ferrite Phase in CF3 Cast Stainless Steel

390

  • Yong Yang, Zhangbo Li (Univ. Florida)

Neutron Irradiation of Nuclear Structural Materials Fabricated by Powder Metallurgy with Hot Isostatic Pressing

392

  • Donna P. Guillen (INL), Janelle P. Wharry (Purdue Univ.), David W. Gandy (EPRI)

Post Irradiation Examination of Fast Neutron Irradiated 14YWT Tubes at Nuclear Science User Facilities

394

  • T. A. Saleh (LANL), D. L. Krumwiede (Univ. California, Berkeley), E. Aydogan, M. E. Quintana, T. J. Romero (LANL), P. Hosemann (Univ. California, Berkeley), S. A. Maloy (LANL)

Accident Tolerant Fuels

397

Multi-Functional Zirconium-Silicide Coatings on Zirconium-alloy for Improved Accident Tolerance

399

  • Hwasung Yeom, Hangjin Jo, Benjamin Maier, Michael Corradini, Kumar Sridharan (Univ. Wisconsin, Madison), Gi Cheol Lee, Hyunwoo Noh, Tong Kyun Kim, Moo Hwan Kim, Hyun Sun Park (Pohang Univ. of Sci. and Technol.)

Interdiffusion Behavior of U3Si2 and FeCrAl via Diffusion Couple Studies

403

  • Rita Hoggan, Jason Harp, Lingfeng He (INL)

A Modified Embedded-Atom Method Interatomic Potential for U-Si

407

  • Benjamin Beeler (INL), Michael Baskes (LANL & Unic. California, San Diego & Mississippi St. Univ), David Andersson (LANL), Yongfeng Zhang (INL)

Pressure Loading with In-Situ Permeability Measurement of SiC Ceramic Matrix Composite Tube

410

  • K.S. Shapovalov, G.M. Jacobsen, G. Vasudevamurthy, C.P. Deck (General Atomics)

Accident Tolerant Fuel Cladding Tube Irradiations in the HFIR

413

  • Christian M. Petrie, Kurt A. Terrani, Yutai Katoh (ORNL)

Oxidation of Advanced Steel Cladding Alloys in Extreme Environments

417

  • Mohamed Elbakhshwan, Simerjeet K. Gill, Abdul Rumaiz (BNL), Clive Clayton, Michael Cuiffo (Stony Brook Univ.), Raul Rebak (General Electric), Lynne E. Ecker (BNL)

Improvements to Modeling Capabilities of ATF Concepts in the BISON Fuel Performance Code

419

  • Kyle A. Gamble, Danielle M. Perez, Jason D. Hales (INL)

Estimation of Core Recovery Time with TRACE

422

  • Anil Gurgen, Koroush Shirvan (MIT)

Post Irradiation Examination and Advanced Measurement Techniques—I

427

Neutron Irradiation Effects on Thermal and Mechanical Properties of NITE-SiC

429

  • Kurt Terrani, Caen Ang, Takaaki Koyanagi, Wallace Porter (ORNL)

Precipitation of Epsilon Particles in Metal Doped Ceria Irradiated with Energetic Ions

431

  • Weilin Jiang, Michele Conroy, Ram Devanathan (PNNL), Caitlin Taylor, Khalid Hattar (SNL), Johnathan Gigax, Lin Shao (Texas A&M)

Tungsten Foils and Composites for Fusion Applications - Mechanical Testing

435

  • Jeremy Moon (Univ. Nevada, Reno), Lauren Garrison (ORNL)

The Plan for Post-Irradiation Examination of Zion Reactor Pressure Vessel Beltline Materials

438

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

Preliminary Analysis of Damage to MPFDs Caused by Reactor Pulses

441

  • Mark J. Harrison, Michael A. Reichenberger, Daniel M. Nichols, Douglas S. McGregor, Jeremy A. Roberts (Kansas St. Univ.)

Post-Irradiation Examination for Conventional and Advanced Nuclear Fuel

444

  • V. V. Rondinella, T. A. G. Wiss, D. Papaioannou, S. Bremier, D. Bottomley, D. Staicu, P. Pöml, M. Marchetti, F. Cappia (European Commission, JRC)

Comparison of Thermal Diffusivity Degradation of Irradiated Zirlo and SiC-SiC Composite

446

  • Zilong Hua (Utah St. Univ.), Shuyan Kong, Peng Yan, Yanhong Liu (State Power Investment Corporation Central Research Institute), Yuefang Dong (Utah St. Univ.), Haihong Xia (State Power Investment Corporation Central Research Institute), Heng Ban (Utah St. Univ.)

Post Irradiation Examination and Advanced Measurement Techniques—II

449

Steam Corrosion Investigation of Single Silicon Carbide Nanostructures

451

  • Md. Ruhul Amin Shikder, Arunkumar Subramanian (Univ. Illinois at Chicago), Gokul Vasudevamurthy, Christian P. Deck (General Atomics)

Nondestructive Evaluation of Alkali-Silica Reaction in High-Strength Concrete for Aging Structures Sustainability

453

  • Alexander Heifetz, Sasan Bakhtiari, Juan Lu, (ANL), Anthony Bentivegna (Construction Technology Laboratory)

Evaluation of Optical Fiber Bragg Gratings in a Nuclear Reactor

457

  • Brandon A. Wilson, Tony Birri, Thomas E. Blue (Ohio State)

Optimization of Silica Optical Fiber for High Temperature, Radiation Environments

461

  • Brandon A. Wilson, Kelly M. McCary, Thomas E. Blue (Ohio State)

Helium Irradiation Tolerance of Ti3SiC2 MAX Phase Material

465

  • Hongliang Zhang, Ranran Su, Liqun Shi (Fudan Univ.), D. J. O'Connor (Univ. Newcastle)

Deposition of Ti2AlC Thin Film

468

  • Ranran Su, Hongliang Zhang, Liqun Shi (Fudan Univ.)

Neutron Generator Driven Active Nuclear Fuel Scanner

472

  • Ross Radel, Mark Thomas, Chris Seyfert, Evan Sengbusch, Eli Moll (Phoenix Nuclear Labs)

Nuclear Fuels

475

A Theoretical Investigation of the Chemical Behaviour of Irradiated U-Mo/Mg Fuel

477

  • M. H. A. Piro (Univ. Ontario Inst. Technol.)

Coupling Experiments and Simulations to Understand Metallic Fuel Behavior

479

  • Assel Aitkaliyeva (INL/Univ. Florida), Cynthia Papesch (INL), Michael Tonks (Penn State)

Uniaxial Ratcheting and Fatigue Failure of SA508-3 at Elevated Temperature

481

  • Jun Tian, Yu Yang (Nuclear Power Institute of China), Qianhua Kan (Southwest Jiaotong Univ.)

Effect of Interaction Layer and U-Mo Size on Pore Growth in U-Mo/Al Fuel

483

  • Gwan Yoon Jeong (UNIST), Yeon Soo Kim (ANL), Dong-Seong Sohn (UNIST)

Small-Scale Mechanical Testing of UO2

485

  • D. Frazer (Univ. California, Berkeley), B. Shaffer, K. Roney, H. Lim, B. Gong, P. Peralta (Arizona St. Univ.), P. Hosemann (Univ. California, Berkeley)

Correlation between Grain Size Distribution and Grain Boundary Character in Polycrystalline Uranium Dioxide

488

  • K. Rudman, B. Shaffer, H. Lim, R. Mcdonald, P. Peralta (Arizona St. Univ.)

Effect of Recrystallization on Gas Bubble Swelling in UMo Fuels

492

  • Shenyang Hu, Curt A. Lavender, Vineet Joshi (PNNL)

Nuclear Fuels and Materials in Fast Reactors

497

A Phase-Field Model for the U-Pu-Zr System

499

  • Jacob Hirschhorn (Penn. State), Assel Aitkaliyeva, (Univ. Florida, INL), Cynthia Papesch (INL), Michael Tonks (Penn. State)

A Potential Mechanism for Lanthanide Transport in Metallic Fuels

501

  • Cetin Unal, C. Matthews (LANL), L. Xiang, J. Isler, J. Zhang (Ohio State), J. Galloway (LANL)

Advanced Simulation Aided Metallic Fuel Design

504

  • C. Matthews, J. Galloway, C. Unal (LANL)

Evaluation of the Thermophysical Properties and Microstructure of UPu24Zr15 Metallic Fuel

507

  • Scott Middlemas, Cynthia A. Papesch (INL), Assel Aitkaliyeva (INL/Univ. Florida)

Phase Verification and Thermophysical Properties Evaluation of Pu-Zr Alloys

508

  • Cynthia Papesch (INL), Assel Aitkaliyeva (INL/Univ. Florida), Scott Middlemas (INL)

Statistical Analysis in Support of Fuel Temperature Control in the Advanced Gas Reactor Experiments

510

  • Binh T. Pham, Nancy J. Lybeck, Grant L. Hawkes, Jeffrey J. Einerson (INL)

Serrated Yielding in Alloy 709 at 500 °C

514

  • A. S. Alomari, N. Kumar, K. L. Murty (NCSU)

Advanced Manufacturing

517

Design and Test of Self-Lubricating Bearing for High Temperature Gas-Cooled Reactor

519

  • Qinzhao Zhang, Hong Wang (Tsinghua Univ.)

Understanding Manufacturing Scale-Up of Plasma Sprayed Zr Barrier Coatings on U-10Mo Fuels

520

  • Dustin R. Cummins, Kendall J. Hollis, Cheng Liu, James A. Valdez, David E. Dombrowski (LANL)

Research of Materials and Components for Molten Salt Reactors

523

  • Martina Koukolíková, Peter Sláma, Zbyšek Nový (COMTES FHT Inc.), Pavel Svoboda, Petr Toman (MICo Ltd.), Martin Mareček, Jan Uhlíř (Research Centre Rez)

MATHEMATICS AND COMPUTATION

Current Issues in Computational Methods–Roundtable

529

Monte Carlo Methods

531

Variance Estimation in Monte Carlo Eigenvalue Simulations Using Spectral Analysis Method

533

  • Jin Lei (Texas A&M Univ., Corpus Christi), Kaushik Banerjee, Steven P. Hamilton, Gregory G. Davidson (ORNL)

Error Convergence Characterization for Stochastic Transport Methods

536

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

A Comparison of the FW-CADIS and MR-CADIS Variance Reduction Methods

540

  • Douglas E. Peplow (ORNL)

Spherical Kernel Density Estimators For Monte Carlo Radiation Transport Problems

544

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

Implementation of Weighted Delta-Tracking with Scattering in the Serpent 2 Monte Carlo Code

548

  • J. S. Rehak (Univ. California, Berkeley), L. M. Kerby (INL, Idaho State), M. D. DeHart (INL), R. N. Slaybaugh (Univ. California, Berkeley), J. Leppänen (VTT Technical Research Centre of Finland)

Advancement of Functional Expansion Tallies Capabilities in Serpent 2

552

  • Brycen Wendt, Leslie Kerby (Idaho St. Univ. & INL), Aaron Tumulak (LANL), Jaakko Leppänen (VTT Technical Research Centre Finland), Mark DeHart (INL)

Computational Methods and Mathematical Modeling

557

Determining Physical Parameters of Shielded Uranium using Gamma Spectroscopy and the DiffeRential Evolution Adaptive Metropolis (DREAM) Method

559

  • Justin R. Knowles, Keith C. Bledsoe, Jordan P. Lefebvre, Matthew A. Jessee (ORNL)

Solving Inverse Transport Problems with Neutron Multiplication Measurements and Improved Differential Evolution

563

  • Keith C. Bledsoe, Jordan P. Lefebvre, Justin R. Knowles (ORNL)

Addressing Over-Solving in Multiphysics Codes with Nested Solvers

567

  • Jaron P. Senecal, Wei Ji (Rensselaer Polytechnic Inst.)

Flux in a 1D-Reactor Cell by Response Matrix

570

  • B. D. Ganapol (Univ. Arizona), D. W. Nigg, D. S. Crawford (INL)

Investigation of Xenon Oscillations via Point Kinetics

574

  • B. Ganapol (Univ. Arizona), F. Gleicher, R. Martineau (INL)

Recovering Topology of Nested Volumes Represented by Single Closed Surfaces

578

  • Chelsea A. D'Angelo, Andrew Davis, Paul P. H. Wilson (Univ. Wisconsin, Madison)

Analysis of the VERA Core Physics Benchmark Problems using cosRMC Code

582

  • Yao Qin, Hui Yu, Guoping Quan, Yixue Chen (State Nuclear Power Software Development Center)

The Parareal Method for Solving Space-Dependent Neutron Kinetics Equations in Hexagonal-z Geometry

585

  • Yun Cai (Tsinghua Univ. & Nuclear Power Institute of China), Jingjing Hou (Nuclear Power Operation Management Co.), Xingjie Peng, Qing Li (Nuclear Power Institute of China), Kan Wang (Tsinghua Univ.)

Uncertainty Quantification and Sensitivity Analysis—I

589

Application of Polynomial Chaos Expansion in One-Dimensional Inverse Transport Problems

591

  • Keith C. Bledsoe, Matthew A. Jessee, Jordan P. Lefebvre (ORNL)

Second-Order Uncertainty Analysis for Radiation Shielding Problems Using MCNP

595

  • Jeffrey A. Favorite, Tom Burr (LANL)

Adjoint-Based Constant-Mass Partial Derivatives

599

  • Jeffrey A. Favorite (LANL)

Monte Carlo Estimates of Eigenvalue Sensitivity to System Dimensions using Kernel Density Estimators

603

  • Timothy P. Burke, Brian C. Kiedrowski (Univ. Michigan)

Dakota-MCNP Coupling for Uncertainty Quantification using Polynomial Chaos Expansions

607

  • K. Combs, T. Palmer (Oregon State)

VUSAT - A VERA-CS Uncertainty and Sensitivity Analysis Toolkit

611

  • Hongbin Zhang (INL), Cameron Brown (NCSU), Ling Zou, Haihua Zhao (INL)

Uncertainty Quantification and Sensitivity Analysis for Coupled VERA-CS and FRAPCON

615

  • Cole Blakely, Heng Ban (Utah State), Hongbin Zhang (INL)

Uncertainty Quantification and Sensitivity Analysis—II

619

Statistical Analyses of Post Irradiation Experiments of the BWR Forsmark

621

  • Volker Hannstein, Fabian Sommer (GRS GmbH)

Uncertainty and Sensitivity Analysis of TREAT Transient Test #15

625

  • Congjian Wang, Sebastian Schunert, Paul W. Talbot, Benjamin Baker, Yaqi Wang, Javier Ortensi, Frederick Gleicher, Mark DeHart, Cristian Rabiti (INL)

Kriging-Based Inverse Uncertainty Quantification of BISON Fission Gas Release Model

629

  • Xu Wu, Tomasz Kozlowski (Univ. Illinois, Urbana–Champaign)

Sensitivity Coefficients for Diffusion Coefficients and Other Reactor Physics Parameters using CE TSUNAMI-3D

633

  • Christopher Perfetti, Matthew Jessee, Bradley Rearden (ORNL)

Deterministic Transport Methods

637

Diffusion Synthetic Acceleration for High Order Sn Transport on Meshes with Curved Surfaces

639

  • Douglas N. Woods, Todd S. Palmer (Oregon State)

Convergence Study of LR-NDA Using Fourier Analysis

643

  • Sicong Xiao, Kangyu Ren, Dean Wang (Univ. Mass., Lowell), Yunlin Xu, Thomas J. Downar (Univ. Michigan)

A Continuous-Discontinuous Hybrid Finite Element Method for S N Transport

647

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

Direct SN Treatment of the Scattering Source with Phase Functions

650

  • Vincent Laboure, Yaqi Wang, Sebastian Schunert (INL)

Flexible Spatial Partitions in MPACT Through Module-Based Data Passing

654

  • Shane Stimpson, Benjamin Collins (ORNL)

Calculation of Higher Eigenpairs of the Transport Equation Using IRAM Based on Domain Decomposition

658

  • Wenbin Wu, Yingrui Yu, Qing Li (Nuclear Power Inst. of China)

NUCLEAR CRITICALITY SAFETY

Data, Analysis and Operations in Nuclear Criticality Safety—I

665

Measurement of Delayed Neutron Group Parameters Using the Fission Burst of CFBR-II

667

  • Lingli Song, Chun Zheng (Inst. Nuclear Physics and Chemistry CAEP)

Criticality Scoping Calculations for a Multi-Function Dissolver Insert

669

  • Tracy Stover, Stephen Kessler (SRNS)

Bounding the Chemistry Conditions in the HM Solvent Extraction Process Criticality Safety Analyses

673

  • Tracy Stover, Stephen Kessler, John Lint (SRNS)

Moderation Control Challenges in a Shutdown Facility

678

  • Tom Hines (DOE), Matthew Wilson (Paschal Solutions Inc.)

A New Look at Historic CRAC “Divergence” Experiments—Implications for a CAAS Minimum Accident of Concern

682

  • Peter L. Angelo (Y-12 National Security Complex)

Considerations for Using FGE Conversion Factors in Type A Shipping Packages at the Savannah River Site

687

  • Brittany Williamson, James Baker (Savannah River Nuclear Solutions)

The Difficulty of Defining the Terms “Credible” and “Unlikely” for Nuclear Criticality Safety Purposes

689

  • Douglas G. Bowen (ORNL)

Data Analysis and Operations in Nuclear Criticality Safety—II

691

Open Source Release of NJOY2016 and NJOY21

693

  • Jeremy Lloyd Conlin, A. C. Kahler, Austin P. McCartney (LANL)

LANL-SNL Collaboration on NCS Validation

697

  • Forrest B. Brown (LANL), John A. Miller, Shawn J. Henderson (SNL), Michael E. Rising, Jennifer L. Alwin (LANL)

Study of Whisper Statistics for Criticality Safety Code Validation

701

  • Natasha Glazener, Trevor Stewart, Alan Yamanaka (LANL)

Full Law Analysis Scattering System Hub (FLASSH)

705

  • Y. Zhu, A. I. Hawari (NCSU)

Semi-Analytical Benchmarks for MCNP6

709

  • Pavel Grechanuk (Oregon State), Michael E. Rising, Forrest B. Brown (LANL), Todd S. Palmer (Oregon State)

The Half Monte Carlo Method: Combining Total Monte Carlo with Nuclear Data Sensitivity Profiles

712

  • I. Hill, J. Dyrda, (OECD Nuclear Energy Agency)

Status of a New Resonance Evaluation for Cerium to Support Nuclear Criticality Safety Applications

714

  • Vladimir Sobes, Klaus Guber (ORNL)

Data, Analysis and Operations in Nuclear Criticality Safety—III

719

Effects of Boron and Graphite Uncertainty in Fuel for TREAT Simulations

721

  • Kyle Vaughn,  Zander Mausol, Esteban Gonzalez (Univ. Florida), Mark DeHart (INL), Sedat Goluoglu (Univ. Florida)

Combining RHF and HFIR Disposition Campaigns—Analysis, Opportunity, and Lessons Learned

724

  • Tracy Stover, John Lint (SRNS)

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

729

Nuclear Criticality Safety Division Pioneer Discussion–Panel

731

ANS-8 Standards Forum

733

NUCLEAR INSTALLATIONS SAFETY

Recent Trends in Probabilistic Safety/Risk Assessment for Nuclear Power Plants–Panel

737

Nuclear Installations Safety: General

739

Radiological Source Term Estimates of the Fukushima Daiichi Nuclear Accident

741

  • Matthew J. Krupcale, John C. Lee (Univ. Michigan), Theodore W. Bowyer (PNNL)

Study of Control Rod Device Mechanism Missile Impact on Protection Plate

744

  • Xianhui Ye, Furui Xiong, Bin Zhen, Naibin Jiang (Nuclear Power Institue of China)

LOCA Analysis for the NIST Research Reactor

747

  • Joo Seok Baek, Lap-Yan Cheng, David Diamond (BNL)

Evaluation of the New Boron Model of the TRACE Code

750

  • Juan J. Carbajo (ORNL)

Deterministic Selection of Design Extension Condition without Core Melt

754

  • Jong Ho Choi, Min Shin Jung and Gyu Cheon Lee (KEPCO)

Power Distribution Control Strategy of the Soluble Boron Free SMR

757

  • Jinhan Bae, Jaeshik Kim, Sungju Kwon, Jinyoung Lee, Kibong Seong (KEPCO NF)

Demonstration of Passive Phoretic Decontamination by Accident Simulation in a Scaled Reactor Containment

760

  • Sola Talabi (Pittsburgh Technical)

Nuclear Safety R&D at the Department of Energy

763

Dexerity and Worker Comfort in an Ergonomically Designed Glovebox Glove

765

  • Martha Chan, Cindy Lawton, Lawrence Ticknor (LANL)

Development of CFD Flow Analysis for Nuclear Facility Ventilation Systems

767

  • Philip Strons, James L. Bailey (ANL)

Fragmentation Prediction for a Brittle Ceramic: An Integrated Two-Scale Model Approach

769

  • Christopher J. O'Brien, Pierre-Alexandre Juan, John Bignell, Rémi Dingreville (SNL)

Characterizing the Benefits of Seismic Isolation of Nuclear Structures in Terms of Reduced Risk and Cost

773

  • Chandrakanth Bolisetti (INL), Chingching Yu (Univ. Buffalo, SUNY), Justin Coleman (INL), Ben Kosbab (SC Solutions), Andrew Whittaker (Univ. Buffalo, SUNY)

High Performance-Multidisciplinary Simulation  for Regional Scale Earthquake Hazard and Risk Assessments

777

  • Floriana Petrone (LBNL), Jenna Wong (LBNL & San Francisco State), Mamun Miah (LBNL), Artie Rodgers, Anders Petersson (LLNL), David McCallen (LBNL & Univ. California)

Thermal Testing of Waste Packages for a Storage Environment

779

  • Victor G. Figueroa, Douglas Ammerman, Carlos Lopez, Walt Gill (SNL)

Preliminary Analysis of FFTF Loss-of-Flow Tests with SAS4A/SASSYS-1

783

  • Guanheng Zhang, Anton Moisseytsev, Tyler Sumner, Thomas Fanning (ANL)

Risk Aspects of Advanced Reactor Technologies Supported by GAIN–Panel

787

Current Topics in Probabilistic Risk Analysis

789

Assembling Multiple Models within the RAVEN Framework

791

  • A. Alfonsi, C. Rabiti, D. Mandelli (INL)

Uncertainty Quantification for External Events Analysis of LWRS/RISMC Project

795

  • Carlo Parisi, Andrea Alfonsi, Cristian Rabiti, Ronaldo H. Szilard (INL)

Electrical Cross-Tie Option & Issues to Cope With Extended Station Blackout

798

  • Jun Su Ha, Jamila Khamis Alsuwaidi (Khalifa Univ.), Sung-yeop Kim (KAERI)

Preliminary Study for Development of Technical Basis of Quantitative Safety Goals for NPPs Operations in UAE

801

  • Osama Ali Al Shehhi (Federal Authority for Nuclear Regulation), Jun Su Ha, Young-Ji Byon, Chung Suk Cho (Khalifa Univ.), Sung-yeop Kim (KAERI)

Examining the Effect of Plume Rise on Radiological Consequences of Nuclear Accidents

804

  • Sana Ullah, Man-Sung Yim (Korea Advanced Inst. of Sci. and Tech.)

Sensitivity Analysis of Successful Evacuee Proportion in Hypothetical NPP Accident by Earthquake

808

  • Sung-yeop Kim, Ho-Gon Lim, (KAERI)

NUCLEAR NONPROLIFERATION POLICY

Advancing Global Nuclear Energy and Strengthening National Security–Panel

815

Establishing and Advancing Nonproliferation and Nuclear Policy Education at U.S. Nuclear Science and Engineering Programs–Panel

817

Nuclear Nonproliferation Policy: General

819

Research on the IAEA State-Level Safeguards Approach in KAERI

821

  • Juang Jung, Hyun-Jo Kim, Hyun-Suk Kim, Sung-Ho Lee, In-Chul Kim, Byung-Doo Lee (KAERI)

Barcode Testing for the Global Identifier for UF6 Cylinders

823

  • Jessica L. White-Horton, James R. Garner, J. Michael Whitaker (ORNL)

The Nuclear Weapons and Strategy Minor at the United States Air Force Academy

826

  • Ryan Cress, Kirk Brown (U.S. Air Force Academy)

OPERATIONS AND POWER

Hybrid Energy Systems

831

Experimental Capability for Preparation and Purification of Molten Salts to Support Advanced Reactor Concepts, Nuclear Hybrid Energy Systems and Dynamic Grid Energy Storage Concepts

833

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

Technology Options for Integrated Thermal Energy Storage in Nuclear Power Plants

837

  • Daniel Curtis, Natalie Shifflet, Charles Forsberg (MIT)

Economic Assessment of Nuclear Hybrid Energy Systems: Optimization using RAVEN

841

  • Aaron S. Epiney, Andrea Alfonsi, Cristian Rabiti, Jun Chen (INL)

Models and Simulation Environment for the Design and Optimization of Hybrid Energy Systems

845

  • Richard B. Vilim, Roberto Ponciroli (ANL), Thomas Harrison, Lou Qualls (ORNL)

Using Dynamic Line Rating to Enhance Flexibility of Wind-Involved Hybrid Energy System

849

  • Wei Zhang, Katya L. Blanc, Timothy R. McJunkin, Jake P. Gentle (INL)

New Nuclear Construction around the World–Panel

853

Thermal Energy Storage Systems and their Integration with NPPs

855

Development Strategy for Gas Turbines with Firebrick Resistance-Heated Energy Storage to Enable Nuclear-Renewable Grid Integration

857

  • Charles Forsberg (MIT)

Heat Storage for Peak Power with Base-Load Rankine-Cycle LWRs and Brayton-Cycle High-Temperature Reactors

862

  • Charles Forsberg (MIT)

An Evaluation of Energy Storage Options for Nuclear Power

866

  • Samuel C. Johnson, Michael E. Webber (Univ. Texas, Austin), Justin L. Coleman (INL)

Using Conductive Firebrick Resistance Heating to Enable Very High-Temperature Heat Storage in Nuclear Gas Turbine Systems

870

  • Daniel C. Stack, Charles Forsberg (MIT)

Steam Accumulator Storage Integration into a Nuclear Power Plant

874

  • Seth Bisett, Alina LaPotin, Erich Schneider (Univ. Texas, Austin)

Performance of Energy Storage with Nuclear and Renewable Power Systems

878

  • Benjamin Vegel (Utah State), Jason C. Quinn (Colorado State), Piyush Sabharwall (INL)

Operations and Power: General

883

An Unsteady State Gas Transport Model in Matrix Laboratory (MATLAB) for PWR Gas Management

885

  • Danial S. Soorty, Wayne M. Gibson (ChemStaff, Inc.)

Quantification of Functional Impact Classification on the Current U.S. Nuclear Fleet

889

  • Sarah M. Ewing, Nancy Johnson, Piyush Sabharwall (INL)

Measurement of Nuclear Power Plant Construction Performance Using EVMS Model

893

  • Myung S. Roh, Eun I. Lee (KEPCO)

Diverting Steam from a Nuclear Power Plant to Thermal Storage to Increase Economic Efficiency of Electricity Production

897

  • Natalie Shifflet, Daniel Curtis, Charles Forsberg (MIT)

Progress in Development of Fluoride-Salt-Cooled High-Temperature Reactors (FHRs)

900

  • C. W. Forsberg, L.-W. Hu (MIT), P. F. Peterson, M. Fratoni (Univ California, Berkeley), K. Sridharan (Univ Wisconsin, Madison), E. Blandford (Univ New Mexico)

RADIATION PROTECTION AND SHIELDING

Radiation Protection and Shielding: General

907

Reconstructing Solar Particle Event Spectra from Absorbed Dose Measurements

909

  • Amir A. Bahadori, Jeremy A. Roberts (Kansas State), Martin Kroupa (Leidos), Dan J. Fry (NASA Johnson Space Center)

Initial Modeling of Urban Search Measurements

913

  • Douglas E. Peplow, Mathew W. Swinney, Gregory G. Davidson, Andrew D. Nicholson, Bruce W. Patton (ORNL)

Characterization of NORM in an Urban Environment using HPGe Measurements and MCNP6 Simulations

917

  • Mathew W. Swinney, Douglas E. Peplow, Andrew D. Nicholson (ORNL)

Selective Shielding Bone Marrow: An Approach to Create Personal Protective Equipment for Gamma Radiation

921

  • Gideon Waterman, Kenneth Kase, Oren Milstein, (StemRad Ltd.)

Absolute Dosimetry Model of the University of Washington Clinical Neutron Therapy System (CNTS)

925

  • Gregory Moffitt (Univ. Utah), Robert Stewart, George Sandison (Univ. Washington), Tatjana Jevremovic (Univ. Utah)

Validation of Methodology to Simulate Gamma Doses from Historical Weapons Tests

929

  • Thomas M. Miller, Bruce W. Patton (ORNL)

Latent Effects of Radiation on Li-ion Batteries in Robots

934

  • Chuting Tan, Nicholas H. Bashian, Chase W. Hemmelgarn, Wesley J. Thio, Daniel J. Lyons, Yuan F. Zheng, Lei R. Cao, Anne C. Co (Ohio State)

Computation Tools for Radiation Protection and Shielding

937

Neutron & Gamma Correlations using CGM in MCNP 6.2.0

939

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

New Features of TRIPOLI-4® Version 10

943

  • The TRIPOLI-4® Project Team: Fadhel Malouch, Emeric Brun, Cheikh Diop, François-Xavier Hugot, Cédric Jouanne, Yi-Kang Lee, Fausto Malvagi, Davide Mancusi, Alain Mazzolo, Odile Petit, Jean-Christophe Trama, Thierry Visonneau and Andrea Zoia (CEA)

Testing Nesting DXTRAN Spheres for Neutron Transport in Air

945

  • M. L. Fensin, K. C. Kelley, J. S. Hendricks, B. W. Cox, J. T. Goorley, S. S. McCready (LANL)

Speed and Memory Improvements to MCNP6 Delayed-Gamma Line Treatment

949

  • J. R. Tutt, G. W. McKinney (LANL)

Using the MCNP6.2 Correlated Fission Multiplicity Models, CGMF and FREYA

953

  • Michael E. Rising, Avneet Sood (LANL)

Enhanced Monte Carlo Simulation of the Voxel Phantom Lattice Submersed in a Contaminated Air Environment

957

  • Ken Veinot (Easterly Scientific & Y-12 National Security Complex), Shaheen A. Dewji, Mauritius Hiller (ORNL), Keith Eckerman, Clay Easterly (Easterly Scientific)

Highlights of RPSD-2016/ICRS-13—I

961

Improvements in Electron-Photon-Relaxation Data for MCNP6

963

  • H. Grady Hughes and David A. Dixon (LANL)

Activation Calculation for the Dismantling and Decommissioning of a Light Water Reactor Using MCNP™ with ADVANTG and ORIGEN-S

966

  • Luc Schlömer, Sven Tittelbach, Peter-W. Phlippen, Roger Vallentin (WTI GmbH), Bernard Lukas (EnBW Kernkraft GmbH)

Generation of an Activation Map for Decommissioning Planning of the Berlin Experimental Reactor-II

970

  • Nicole Guilliard, Janis Lapins, Wolfgang Bernnat (Univ. Stuttgart - IKE)

Neutron-Gamma Flux and Dose Calculations in a Pressurized Water Reactor (PWR)

974

  • Mariya Brovchenko, Benjamin Dechenaux (IRSN), Kenneth Burn, Patrizio Console Camprini (ENEA), Isabelle Duhamel (IRSN), Arthur Peron (Contractor)

Highlights of RPSD-2016/ICRS-13—II

979

Radiological Shielding Design for the Neutron Backscattering Spectrometer EMU

981

  • T. Ersez, F. Esposto, N. R. de Souza (Australian Nuclear Science & Technology Organisation)

Feasibility Study on Real-Time γ-Ray Spectrum / Dose Measurement System

985

  • Mina Kobayashi, Fuminobu Sato, Isao Murata (Osaka Univ.)

Evaluation of RAPID for a UNF cask benchmark problem

989

  • Valerio Mascolino, Alireza Haghighat, Nathan J. Roskoff, (Virginia Tech)

Examples of Use of SINBAD Database for Nuclear Data and Code Validation

993

  • Ivan Kodeli (Jožef Stefan Institute)

Using the MCNP Taylor Series Perturbation Feature (Efficiently) for Shielding Problems

997

  • Jeffrey A. Favorite (LANL)

REACTOR PHYSICS

Reactor Physics: General—I

1003

PARCS Analysis of the APR1400 Initial Core

1005

  • Andrew Bielen, Peter J. Yarsky (U.S. NRC)

Improvements to PHISICS/RELAP5-3D© Capabilities for Simulating HTGRs

1009

  • Paolo Balestra (Sapienza Univ.), Andrea Alfonsi, Gerhard Strydom, Cristian Rabiti (INL), Fabio Giannetti, Gianfranco Caruso (Sapienza Univ.)

Study on the Technology for Enhancing Element Value by Neutron Transmutation in Light Water Reactors

1013

  • Hiroki Takezawa, Naoyuki Takaki (Tokyo City Univ.)

Reactivity Worth Measurment of Control Rods of CFBR-II with Inverse Kinetics Method

1014

  • Yanpeng Yin, Haojun Zhou, Meng Li (CAEP)

The Neutron Chase: Taking Advantage of EveryNeutron

1017

  • Florent Heidet (ANL)

Reactors Physics: General—II

1019

Optimization of a Monte Carlo Model of the Transient Reactor Test Facility

1021

  • Kristin Smith (Univ. Florida), Mark DeHart (INL), Sedat Goluoglu (Univ. Florida)

Development and Test of a New Verification Scheme for Transient Core Simulators

1025

  • C. Demazière, V. Dykin, K. Jareteg (Chalmers Univ. Technol.)

Core Reactivity Control for a Soluble Boron Free Small Modular Reactor

1027

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

Core Combination Method of Approximation (CCMA) for Neutron Fluence Calculation

1030

  • Yang Wankui, Yuan Baoxin, Zhang Songbao (INPC of CAEP)

Study on Reactor Physical Module Method Used in THR Simulator

1034

  • Wei Chunlin, Sui Zhe, Sun Jun (Tsinghua Univ.)

Reactor Physics: General—III

1037

Simulation of the RPI Reactor Critical Facility Core Using High-Fidelity Neutronics Code PROTEUS

1039

  • C. H. Lee (ANL), D. J. O'Grady (Univ. Illinois Urbana Champaign), Y. S. Jung, E. R. Shehemon (ANL)

Verification of High-Fidelity Neutronics Code PROTEUS for C5G7 Benchmark Problems

1042

  • Y. S. Jung, C. H. Lee, M. A. Smith (ANL)

Modeling of the SPERT Transients Using SERPENT2 with Time Dependent Capabilities

1045

  • Alex Levinsky, Frederick P. Adams, Vinicius N. P. Anghel (Canadian Nuclear Laboratories), Ville Valtavirta (VTT Technical Research Centre)

Preliminary Development of a Nuclide Inventory Code for HTGR

1049

  • Jian Li, Jian Li, Ding She, Lei Shi (Tsinghua Univ.)

Time Scale Effects on the Temperature Coefficient of Reactivity

1052

  • Wenfeng Liang, Jiangmeng Wang, Qilin Xie (Inst. Nucl. Physics and Chemistry, CAEP)

Analysis of Neutron Spectrum and Control Rod Worth Measurements in Several ZPPR-15 Loadings

1055

  • Gerardo Aliberti, Michael A. Smith, Richard M. Lell, Chang-ho Lee (ANL)

The Effects of Reflector on Core Reactivity for Conceptual Soluble Boron Free SMR

1059

  • Seunghwan Jun, Jinsun Kim, Do Ik Chang, Kibong Seong (KEPCO)

Heavy-Water Moderated, Molten Uranium Cooled Reactor MCNP Model

1062

  • Neal L. Mann (Neal Mann & Associates)

Research and Test Reactors

1067

LOCA and LOFA Safety Margin Analysis for U-10Mo Monolithic LEU Fuel Conversion of the MURR Reactor

1069

  • David Jaluvka, Earl E. Feldman (ANL), J. Charles McKibben, Leslie P. Foyto (Univ. Missouri, Columbia), John A. Stillman, Erik H. Wilson (ANL)

Neutronics Analysis of TREAT Multi-SERTTA Calibration Test Vehicle (Multi-SERTTA CAL)

1073

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

The Radiation Science and Engineering Center Utilizations and Future Developments at Penn State University

1077

  • Kenan Ünlü (Penn State)

CUDA Computation of the Feynman Distribution

1079

  • A. Talamo, Y. Gohar (ANL)

University of Wisconsin Nuclear Reactor Modeling Improvements

1082

  • YoungHui Park, Alexander Swenson, Paul P. H. Wilson (Univ. Wisconsin, Madison)

PLTEMP/ANL Verification for Assemblies Having Five-Layer Fuel Tubes

1086

  • M. Kalimullah, A. P. Olson, E. E. Feldman (ANL)

Reactor Analysis Methods—I

1091

Improved Modelling for the Assembly Discontinuity Factors in the APEC Method

1093

  • Woosong Kim, Yonghee Kim (KAIST)

Heterogeneous Neutron Leakage Model for PWR Pin-by-Pin Calculation

1096

  • Bin Zhang, Hongchun Wu, Yunzhao Li, Liangzhi Cao (Xi'an Jiaotong Univ.)

Thermal Analysis of a Fuel Channel

1099

  • Abdullah Weiss, Xue R. Yang (Texas A&M Univ.-Kingsville)

Study on Neutronics Calculation Method of SCWR with Annular Fuel Assembly

1103

  • Chuanqi Zhao, Liangzhi Cao, Hongchu Wu (Nuclear and Radiation Safety Center)

Artificial Neural Network Modeling for 2-group Pin-Wise Group Constants

1107

  • HwanYeol Yu, Haseeb ur Rehman, Yonghee Kim (KAIST)

MCNP6 and SERPENT2 Performances with Unstructured Mesh Geometry

1111

  • A. Talamo, Y. Gohar (ANL), J. Leppänen (VTT Technical Research Centre)

Generalization of NESTLE into a Multi-Energy N-Group Formulation

1114

  • William M. Kirkland, Ondrej Chvala, G. Ivan Maldonado (Univ. Tenn., Knoxville)

Verification of a Multiphysics Code with Method of Manufactured Solutions

1116

  • Jipu Wang, William Martin (Univ. Michigan)

Reactor Analysis Methods—II

1121

Two-Step Analysis of Watts Bar Nuclear 1 Cycle 1 with SCALE/PARCS

1123

  • Kevin Xu (Univ. Michigan), Matthew Jessee (ORNL), Andrew Ward, Thomas Downar (Univ. Michigan)

Surrogate Models for TREAT Transient Calculations

1127

  • Congjian Wang, Paul W. Talbot, Sebastian Schunert, Benjamin Baker, Yaqi Wang, Javier Ortensi, Frederick Gleicher, Mark DeHart, Cristian Rabiti (INL)

Radiolytic Gas Bubbles' Model and its Application to AHR's Transient Neutronics Analysis

1131

  • Wang Liangzi, Yao Dong, Yu Yingrui, Wang Shuai (Nuclear Power Institute of China)

RISMC Industry Application #1 (ECCS/LOCA): Core Characterization Automation: Reference PWR Designs for IA#1

1136

  • Aaron S. Epiney, Carlo Parisi, Andrea Alfonsi, Hongbin Zhang, Ronaldo Szilard (INL)

Implementation of CMFD Acceleration Scheme in PROTEUS-MOC

1140

  • Albert Hsieh, Won Sik Yang (Purdue Univ.)

Effect of Delayed Energy Release on Power Normalization in Reactor Depletion Calculations

1144

  • Miriam A. Rathbun, David P. Griesheimer (Univ. Pittsburgh)

Treatment of Nonuniform Temperature Distribution by Subgroup Method

1149

  • Qingming He (MIT & Xi'an Jiaotong Univ), Liangzhi Cao, Hongchun Wu (Xi'an Jiaotong Univ), Benoit Forget, Kord Smith (MIT)

Spanning the Core Design Space with Binary Perturbations—A Mathematical Investigation

1153

  • Tracy Stover (SRNS), Stephen Kessler (Westinghouse Electric Co.)

Recent Advancements in Liquid and Solid Fuel Molten Salt Reactors—I

1157

Verification of the Coupled Neutronics/Thermal-Hydraulics Code TANSY against the MSFR Benchmark

1159

  • Liangzhi Cao, Tianliang Hu, Hongchun Wu (Xi'an Jiaotong Univ.)

Preliminary Results of Material Flow Controlled MSR Depletion Calculations

1162

  • Gavin Ridley, Ondrej Chvala (Univ. Tenn, Knoxville)

New Czech R&D Program on Fluoride Salt-Cooled Nuclear Reactor Systems

1165

  • Jan Uhlíř, Martin Mareček (Research Centre Rez), Lórant Szatmáry (UJV Rez), Zbyšek Nový (COMTES FHT), Petr Toman (MICo Ltd), Jan Jílek (SKODA JS)

Neutronic Tests of Fluoride Salt Based MSR/FHR Coolants

1167

  • Evžen Losa, Michal Košťál, Vlastimil Juříček, Jan Uhlíř (Research Centre Řež), Jeffrey J. Powers (ORNL), Nicholas R. Brown (ORNL & Penn State), Donald E. Mueller, Bruce W. Patton (ORNL)

Molten Salt Reactor Simulations using MPACT-CTF

1170

  • Benjamin Collins, Cole Gentry, Aaron Wysocki, Robert Salko (ORNL)

Feasibility of a Breed-and-Burn Molten Salt Reactor

1174

  • Michael Martin, Manuele Aufiero, Ehud Greenspan, Massimiliano Fratoni (Univ. California, Berkeley)

Dynamic Analysis of the Next Generation Molten-Salt Breeder Reactor System

1177

  • O. Chvala, M. R. Lish, V. Singh, B. R. Upadhyaya (Univ. Tennessee, Knoxville)

Recent Advancements in Liquid and Solid Fuel Molten Salt Reactors—II

1181

Monte Carlo/CFD Coupling for Accurate Modeling of the Delayed Neutron Precursors and Compressibility Effects in Molten Salt Reactors

1183

  • Manuele Aufiero (Univ. California, Berkeley), Pablo Rubiolo (LPSC-IN2P3), Massimiliano Fratoni (Univ. California, Berkeley)

Two-Dimensional Neutronic and Fuel Cycle Analysis of the LEU-Fueled Transatomic Power Molten Salt Reactor

1187

  • B. R. Betzler, J. J. Powers, A. Worrall (ORNL), S. Robertson, L. Dewan, M. Massie (Transatomic Power Corporation)

Extension of the DIF3D Code for Molten Salt Reactor Analysis

1191

  • Tongkyu Park (Purdue Univ./FNC Technol.), Shengcheng Zhou (Purdue Univ./Xi'an Jiaotong Univ.), Won Sik Yang (Purdue Univ.)

Comparing Sensitivity/Uncertainty Analysis Results for LR-0 Salt Experiments with Salt Reactor Models

1195

  • Jeffrey J. Powers (ORNL), Nicholas R. Brown (ORNL & Penn State), Donald E. Mueller, Bruce W. Patton (ORNL), Evžen Losa, Michal Košťál (Research Center Rez)

Adjusted Graphite Thermal Scattering Data Applied to Fluoride-Salt-Cooled Reactors

1199

  • Lance Maul (Australian Nuclear Science and Technology Organisation)

Use of Spectral Shift to Greatly Improve Uranium Utilization in FHR Designs

1203

  • Vedant Mehta, Dan Kotlyar (Georgia Tech)

Reactor Physics Design, Validation and Operational Experience

1207

Demonstration of Load-Follow Operations with Standalone BISON through VERA

1209

  • Shane Stimpson, (ORNL)

Fast Reactor Core Analysis Using AZNHEX Neutron Diffusion Code

1213

  • Juan Galicia-Aragon, Juan Luis Francois, Guillermo-Elias Bastida-Ortiz (Univ. Nacioanl Autonoma de Mexico), Edmundo del-Valle-Gallegos (Inst. Politecnico Nacional), Armando Gómez-Torres (Inst. Nacional de Investigaciones Nucleares Carretera Mexico)

A Fully Passive Daily Load-Follow Operation in a Small PWR System

1217

  • Ahmed Amin E. Abdelhameed, Yonghee Kim (KAIST)

AZTRAN and AZKIND Verification with a BWR Study Case

1221

  • Guillermo-Elías Bastida-Ortiz, Julio-Amhed Vallejo-Quintero, Juan Galicia-Aragón, Juan-Luis François (Univ. Nacional Autonoma de Mexico), Andrés Rodríguez-Hernández, Armando Gómez-Torres (Inst. Nacional de Investigaciones Nucleares Carretera Mexico), Edmundo del Valle-Gallegos (Inst. Politecnico Nacional)

Investigation of Treat M2 and M3 Calibration Experiments for Benchmark Analysis

1225

  • N. C. Sorrell, A. I. Hawari (NCSU), M. D. DeHart, J. D. Bess (INL)

Verification of AZTRAN v1.2 Code with a PWR-MOX Benchmark Problem

1229

  • Julio-Amhed Vallejo-Quintero, Guillermo-Elías Bastida-Ortiz, Juan-Luis François (Universidad Nacional Autónoma de México), José-Vicente Xolocostli-Munguía, Samuel Vargas-Escamilla (Instituto Nacional de Investigaciones Nucleares Carretera México), Edmundo del Valle-Gallegos (Instituto Politécnico Nacional)

Improved Core Design of the Supercritical Water-Cooled Reactor CSR1000

1233

  • Lianjie Wang, Di Lu, Ping Yang (Nuclear Power Institute of China)

Calculating Control Rod Differential Worth Using Adjoint-Weighted Method

1237

  • Gang Wang, Ganglin Yu (Tsinghua Univ.)

THERMAL HYDRAULICS

Two Phase Flow and Heat Transfer Fundamentals

1243

A New Mechanistic Model of Nucleation Site Density

1245

  • Zeyong Wang, Michael Z. Podowski (Rensselaer Polytechnic Institute)

Evaluation of the Shear Rate Effect on the Interfacial Forces Acting on a Single Bubble

1249

  • Jinyong Feng, Igor Bolotnov (NCSU)

Verification of the Two-Fluid Model in the Spectral Element Code Nek-2P for Adiabatic Flow Conditions

1251

  • Dillon R. Shaver (ANL), Ananias Tomboulides (ANL/Aristotle Univ. Thessaloniki), Aleksandr Obabko, Adrian Tentner, Prasad Vegendla, Elia Merzari (ANL)

Numerical Uncertainties vs. Model Uncertainties in Two-Phase Flow Simulations

1255

  • Ling Zou, Haihua Zhao, Hongbin Zhang (INL)

Analysis of COBRA-TF Critical Heat Flux Models for Triangular Fuel Assembly Pitch

1259

  • Ozlem Aktas Ozulus, Sule Ergun (Hacettepe Univ.)

CFD Simulation of Bubble Growing Under a Downward Facing Surface

1262

  • Tien-Juei Chuang, Yuh-Ming Ferng, Ke-Wei Lai (National Tsing Hua Univ.)

Simulating Bubble Deformations Using the Intersection Marker (ISM) Front-Tracking Method

1265

  • Mark Ho (Australian Nuclear Science and Technology Organisation), Syed Ahsan Sharif (Univ. New South Wales), Guan Yeoh (Australian Nuclear Science and Technology Organisation & Univ. New South Wales), Victoria Timchenko (Univ. New South Wales)

Advances in CTF and Multiphysics Coupling

1269

Validation of CTF Droplet Entrainment and Annular/Mist Closure Models using Riso Steam/Water Experiments

1271

  • Aaron J. Wysocki, Robert Salko (ORNL)

Review of CTF's Fuel Rod Modeling Using FRAPCON-4.0's Centerline Temperature Predictions

1275

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

Implementation of a Pressure Correction Term in the CTF Subchannel Code

1279

  • Marc-Olivier G. Delchini, Robert Salko (ORNL),  Vincent Mousseau (SNL)

Current Verification and Validation Efforts of Multiphysics Packages

1283

Proposed Semi-Analytic Benchmark for Coupled Neutronics/Thermal-Hydraulics Feedback in Multiphysics Simulations

1285

  • David P. Griesheimer, David L. Aumiller, Daniel F. Gill (Bettis Atomic Power Laboratory)

The International Experimental Thermal-Hydraulic Systems Database TIETHYS: A New NEA Validation Tool

1290

  • Yeonjoo Cho (Chung-Ang Univ.), James Dyrda (OECD Nuclear Energy Agency), Kumar Singh Rohatgi (BNL)

Calibration of COBRA-TF and STAR-CCM+ with Dakota 6.5 for CASL

1293

  • Natalie C. Gordon, Lindsay N. Gilkey (SNL)

OECD/NEA EGMPEBV Activities in Multi-Physics Verification and Validation

1297

  • M. Avramova (NCSU), M. DeHart (INL), J. Dyrda (OECD NEA), J.-P. Hudelot (CEA Cadarache), K. Ivanov (NCSU), A. Petruzzi (Nuclear and Industrial Engineering S.r.l), U. Rohatgi (BNL), T. Valentine (ORNL), K. Velkov (Gesellschaft für Anlagen- und Reaktorsicherheit)

Validation of COBRA-TF and STAR-CCM+ with Dakota 6.5 for CASL

1301

  • Lindsay N. Gilkey,  Natalie C. Gordon (SNL)

Experimental Thermal-Hydraulics: High Resolution Experiments—I

1305

Comparing Velocity Profiles Along the Rod Length of a Helical Coil Steam Generator Model

1307

  • Marilyn Delgado, Saya Lee, Yassin Hassan (Texas A&M Univ.)

Processing Methodology for Double Sensor Probe in a Bubbly Flow

1311

  • Chung-Yen Hsu, Jiun-Ren Wang, Tien-Juei Chuang, Yuh-Ming Ferng (National Tsing Hua Univ.)

Visualization of Flow Interaction in a Channel Flow Produced by a Pair of Helically Coiled Rods

1315

  • Saya Lee, Marilyn Delgado, Colin Guilbault, Yassin A. Hassan (Texas A&M Univ.)

Time-Resolved PIV/PTV Measurements on Interior Subchannels of a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle

1318

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

High Resolution Stereoscopic PIV Measurements in a 5x5 Rod Bundle with Mixing Vane

1322

  • Thien Nguyen, Mason Childs, Mateusz Marciniak, Yassin Hassan (Texas A&M Univ.)

Time Analysis on a Steam Condensation Jet

1326

  • Arturo Cabral, Saya Lee, Macon Heath, Yassin A. Hassan (Texas A&M Univ.)

Thermal-Hydraulic Results for the Aboveground Configuration of a Dry Cask Simulator

1330

  • S. G. Durbin, E. R. Lindgren (SNL), A. Zigh, J. Solis (NRC)

Experimental Thermal-Hydraulics—II

1335

Orificed Flow Results for a Two-Phase Natural Circulation Loop

1337

  • Casey A. Tompkins, Michael Corradini (Univ. Wisconsin, Madison)

Single Rod Reflood Quenching Experiments with Simulated Decay Heat for Accident-Tolerant Fuel Claddings

1341

  • Chan Lee, Kwangeun Lee, Wang Kee In, Chang Hwan Shin (KAERI)

Korean Localization Program for the Performance Verification Test of APR1400's RCP

1343

  • Seok Cho, Seok Kim, Byoung-Uhn Bae, Yun-Jae Cho, Yeon-Sik Kim, Woo-Jin Jeon, Young-Jung Yun (KAERI)

Steady State Pool Boiling in Sea Water

1347

  • Tzu Chen Huang, Chin Pan (National Tsing Hua Univ.)

Observation of Downward Facing Pool Boiling on a Hemispherical Vessel under External Reactor Vessel Cooling

1351

  • Xiang Zhang, Wei Lu, Teng Hu (State Nuclear Power Technol. Research & Development), Huajian Chang, Deqi Cheg (Chongqing Univ.)

The Flow Visualization for the Separation of Air-Water Bubbly Two-Phase Flow Through a Vertical T-Junction

1355

  • Jiun-Ren Wang, Chung-Yen Hsu, Yuh-Ming Ferng (National Tsing Hua Univ.)

Integral Effect Test of ATLAS Facility on Multiple Failure in a Prolonged Station Blackout

1358

  • Byoung-Uhn Bae, Seok Cho, Kyoung-Ho Kang, Yu-Sun Park, Jong-Rok Kim, Nam-Hyun Choi, Ki-Yong Choi (KAERI)

Thermal-Hydraulics: General—I

1363

TRACG Benchmark Study: 2015 Fermi Thermal-Hydraulic Instability Event

1365

  • Alex Miller, Lander Ibarra, Justin Lamy, Juswald Vedovi (GE Hitachi), Paul Kiel (DTE Energy)

Integrating Sudo-Kaminaga Correlation to the Safety Analysis Code PARET-ANL

1369

  • Richard Leos (Texas A&M Univ., Kingsville), Zeyun Wu (NIST/Univ. Maryland), Robert E. Williams (NIST), Xue Yang (Texas A&M Univ., Kingsville)

Sensitivity Studies of the Inter-Subchannel Mixing in Subchannel Analysis

1373

  • Hu Mao, Bao-Wen Yang (Xi'an Jiaotong Univ.)

TRACE Analysis of Loss of Flow for the APR1400

1377

  • Peter Yarsky, Andrew Bielen, Ronald Harrington, William Krotiuk (NRC)

Numerical Analysis of Flow Instability in Once-Through Steam Generator

1381

  • Eui Kwang Kim, Jong Bum Kim, Jiyoung Jeong (KAERI)

Operator Action Time Evaluation of Emergency Water Injection Strategy for Extreme SGTR Accidents

1384

  • Sooyong Park, Kwang-Il Ahn (KAERI)

TORCHE - Toolbox for Reactor Cross-Flow Heat Exchangers

1387

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

Thermal-Hydraulics: General—II

1391

MITR RELAP5 Model Validations at Steady States and Transients

1393

  • Wenwen Zhang (Xi'an Jiaotong Univ./MIT), Yu-jou Wang, (MIT/National Tsing Hua Univ.) Kaichao Sun, Lin-wen Hu (MIT)

Methodology of Experiment Design for Improving Transient Critical Heat Flux Model Development

1397

  • Daniel P. LaBrier, Wade R. Marcum (Oregon State)

Development of Scaling Criteria for Modeling Condensation in Horizontal Tubes Using Reduced Pressure System and Simulant Fluid

1401

  • Khalid Khasawneh, Yong Hoon Jeong (KAIST)

Counterpart Test on IBLOCA of 13% Cold Leg Break in ATLAS Facility

1405

  • Byoung-Uhn Bae, Kyoung-Ho Kang, Yu-Sun Park, Jong-Rok Kim, Nam-Hyun Choi, Ki-Yong Choi (KAERI)

Flow Characteristics of Intermediate Heat Exchanger with CFD Methodology on Nuclear Safety Application

1408

  • Pei-Chi Tseng, Ji-Yang Yu, Xiao-Long Zhang (Tsinghua Univ.), Yuh-Ming Ferng, Chung-Yen Hsu, Ke-Wei Lai (National Tsing Hua Univ)

Computational Thermal-Hydraulics: Computational  Fluid Dynamics—I

1413

Development of a Multiphase Adjoint Capability in OpenFOAM

1415

  • Robert Dacus, Paul Turinsky (NCSU)

A Non-Linear k-ε Turbulent Model Sensitivity Analysis for Flow Across a PWR Spacer Grid with Mixing Vanes

1419

  • Giacamo Busco, Fatih S. Sarikurt, Yassin A. Hassan (Texas A&M Univ.)

Sensitivity Analysis of RANS Modeling on GEMIX CFD Benchmark Study

1424

  • Fatih S. Sarikurt, Yassin A. Hassan (Texas A&M Univ.)

Validation of the Computational Fluid Dynamics Method using the Aboveground Configuration of the Dry Cask Simulator

1428

  • A. Zigh, S. Gonzalez, J. Solis (NRC), S. G. Durbin, E. R. Lindgren (SNL)

Computation of Air Discharge into a Water Pool by Using Volume-of-Fluid Method

1432

  • Ji-Su Kim, Jong Woon Park (Dongguk Univ.)

Influence of Axial Power Distributions on Rod-to-Wall Gap

1436

  • Hongmei Lyu, Bao-Wen Yang, Bin Han (Xi'an Jiaotong Univ.)

Grid Pressure Drop Prediction in a Fuel Assembly

1440

  • Bao-Wen Yang, Bin Han, Yudong Zha (Xi'an Jiaotong Univ.)

Computational Thermal-Hydraulics—II

1445

Thermal Evaluations for Hypothetically Drain-Down Spent Fuel Storage Facility at SRS

1447

  • Si Y. Lee, Dennis W. Vinson (SRNL)

Modelling of the Nuclear Propulsion Rocket

1451

  • Jivan Khatry, Fatih Aydogan (Univ. Idaho)

Modeling the Transient Reactor Test Loop in TRACE for PWR Critical Heat Flux Benchmarking

1455

  • Emory Brown, Wade Marcum (Oregon State), Colby Jensen (INL)

Computational Study of Droplet Dynamics in Dispersed Flow Film Boiling Regime in PWR Geometries

1458

  • Shrey Satpathy, Jun Fang, Igor A. Bolotnov (NCSU)

Improved Safety Injection Flow Map Associated with Target RCS Depressurization to Maintain Core Coolability of OPR1000

1461

  • Joongoo Jeon, Wonjun Choi, Sung Joong Kim (Hanyang Univ.)

Large Eddy Simulation and Direct Numerical Simulation

1465

Heat Transfer Efficiency in Various Prandtl Number Turbulent Flows using DNS Approach

1467

  • Mengnan Li, Jinyong Feng, Igor Bolotnov (NCSU)

Numerical Simulation of Twin Jets using LES with the Nek5000 Code

1471

  • L. B. Carasik (Texas A&M Univ.), E. Merzari (ANL), Y. A. Hassan (Texas A&M Univ.)

Large Eddy Simulation of Turbulent Flow in Rod Bundle with Spacer Grids

1475

  • Wei Zonglan, Chu Xiao, Zhang Yu, Liu Songtao (Nuclear Power Institute of China)

Toward High Fidelity LES Simulations of 5x5 PWR Fuel Bundle with Mixing Vane

1479

  • Fatih S. Sarikurt, Giacamo Busco, Yassin A. Hassan (Texas A&M Univ.)

Direct Numerical Simulation of the Turbulent Flow Through PWR Spacer Grid and Mixing Vanes

1483

  • Jun Fang, Shrey Satpathy, Igor A. Bolotnov (NCSU)

Thermal-Hydraulics of Advanced Reactor and Fuel Concepts

1487

Steady-State Subchannel Thermalhydraulic Assessment of Thorium-Based Fuel Concepts for Use in Pressure Tube Heavy Water Reactors

1489

  • A. Nava Dominguez, Y. F. Rao, A. V. Colton, B. P. Bromley (Canadian Nuclear Laboratories)

Fluoride Salt Static Freezing Study

1492

  • Louis J. Chapdelaine, Raluca O. Scarlat (Univ. Wisconsin, Madison)

Performance Analysis of the Passive Residual Heat Removal System of an Integral Reactor

1496

  • Joo Hyung Moon, June Woo Kee, Seok Kim, Woo Shik Kim, Young In Kim (KAERI)

Scaling of Thermal Stratification in Outlet Plena of SFRS with Gallium as a Surrogate Fluid

1499

  • Brendan Ward, Graham Wilson, Hitesh Bindra (Kansas State), Tyler Sumner (ANL), Rizwan-uddin (Univ. Illinois, Urbana–Champaign)

Modeling the Molten Salt Reactor Experiment with the RELAP5-3D Code

1503

  • Juan J. Carbajo (ORNL), Dane De Wet (ORNL/Univ. California, Berkeley), Nicholas R. Brown (ORNL/Penn State)

Coupled CFD-DEM Analysis of Molten Salt-Cooled Pebble-Bed Reactor Experiment

1506

  • Robert Mardus-Hall (Univ. New South Wales), Mark Ho (Australian Nuclear Science and Technology Organisation), Guan Yeoh (Univ. New South Wales/Australian Nuclear Science and Technology Organisation), Victoria Timchenko (Univ. New South Wales)

Effects of Radiative Heat Transfer in High-Temperature Liquid-Salts

1510

  • Carolyn Coyle, Emilio Baglietto, Charles Forsberg (MIT)

Improved Heat Transfer and Volume Scaling through Novel Heater Design

1514

  • Raleigh Lukas, James Kendrick, Per Peterson (Univ. California, Berkeley)

YOUNG MEMBERS GROUP

Innovations in Nuclear Education–Panel

1521

Workforce Transition: How to Succeed–Panel

1523

Perspectives from Non-Nuclear Energy Sources–Panel

1525

Advocacy and Communication: A Clean Energy Discussion–Panel

1527