Top Fuel 2019

Author Index

Full Issue

PROtect FUEL: The Leading E-ATF Solution Delivered by Framatome

V. Rebeyrolle, N. Vioujard, A. C. Scholer (Framatome Fuel), R. Kliewer, J. Reed (Framatome Inc.)

Westinghouse Chromium-Coated Zirconium Alloy Cladding Development and Testing

John L. Lyons, Jonna Partezana, W. Art Byers, Guoqiang Wang, Arash Parsi, Jorie Walters, Javier Romero, Andrew J. Mueller, Hemant Shah, Robert Oelrich Jr. (Westinghouse)

Coated Fuel Rod for Accident Tolerance and Debris Fret Resistance

Y.-P. Lin, S. DeSilva, D. R. Lutz, M. Connor, S. Michael (GNF), L. Yin, E. J. Dolley, R. B. Rebak (GE Global Research)

Advanced Fuel Technologies of the Future

N. Vioujard (Framatome SAS), R. Kliewer (Framatome Inc.), C. Delafoy (Framatome SAS), J. O’Brian (Framatome Inc.)

GAIA PROtect EATF Lead Fuel Assembly Implementation at Vogtle

Jennifer Baker, Matthew Leonard, Ray Flanery (Southern Nuclear), Scott D’Orio, Robert Clarke, Jeff Reed (Framatome Inc.), Jeremy Bischoff (Framatome SAS)

Development and Validation of Multi-Dimensional Entire Rod Analysis Module for Simulation of Fuel Behavior During LOCA

Sung-Uk Lee, Hyochan Kim, Dong-Hyun Kim (KAERI), Jinsu Kim, Jeong Whan Yoon (KAIST)

The Benefit of International Benchmarks for Extension and Validation of the TRANSURANUS Fuel Performance Code

A. Schubert, Z. Soti, P. Van Uffelen (EC-JRC), M. Ieremenko (State Scientific and Technical Center for Nuclear and Radiation Safety), R. Calabrese (ENEA), S. Boneva, N. Mihaylov, M. Mitev (Inst for Nuclear Research and Nuclear Energy)

Cladding Plasticity Modeling with the Multidimensional Fuel Performance Code OFFBEAT

Alessandro Scolaro (EPFL), Ivor Clifford (PSI), Carlo Fiorina, Andreas Pautz (EPFL)

Qualification of Framatome Fuel Performance Code—GALILEO

Yusen Qi, Chris Allison, Philippe Bellanger, Will Maxson (Framatome), Christophe Garnier (Framatome SAS)

Recent Developments in ARCADIA, Framatome’s Suite of Advanced Core Physics Methods for LWRs

J. Senecal, A. Bennett (Framatome Inc.), M. Riedmann (Framatome GmbH), N. Martin (Framatome Inc.), J. Bigot (Framatome SAS)

Sibling Rod Thermomechanical Modeling with FAST and Comparison to Post-Irradiation Examination Data

Ken Geelhood, Christine Goodson (PNNL)

Characteristics and Performance of ZIRLO Cladding Used Fuel

Guirong Pan (Westinghouse), Rose Montgomery (ORNL), David B. Mitchell (Westinghouse), Brady D. Hanson (PNNL)

Post-Irradiation Measurements on Fuel Rod Plenum Springs for Transport and Reuse of Partly Burnt Fuel

David Schrire (Vattenfall Nuclear Fuel), Klaus Nissen, Udo Fischer, Dominik Streit (Framatome GmbH), Janne Pakarinen (Studsvik AB)

Boundary Conditions to Water Removal from Defective Spent Fuel

Marc Verwerft, Janne Pakarinen, Guy Cornelis (SCK-CEN), Wolfgang Faber (PreussenElektra), Hagen Höfer (Höfer & Bechtel GmbH), Christoph Rirschl (GNS)

Ring Compression Testing of Prehydrided PWR Cladding with Hydride Blisters

M. A. Martin Rengel, J. Ruiz-Hervias (UPM), F. J. Gomez (Advanced Material Simulation), J. M. Rey, C. Alejano (CSN), F. J. Fernandez Lopez, A. Munoz (ENRESA), C. Munoz-Reja, M. Quecedo (ENUSA)

PROtect: Accelerated Implementation of Framatome’s Evolutionary eATF Solution

J. Bischoff, C. Delafoy, N. Chaari, K. Buchanan (Framatome Fuel), E. Schweitzer (Framatome GmbH), K. Nimishakavi, J. Stevens, J. Reed (Framatome Inc.), H. Palancher (CEA), G. Girardin (Kernkraftwerk Gösgen-Däniken AG)

Two-Sided Protection for Zirconium-Based Nuclear Fuel Cladding

F. Addou, A. Michau, H. Maskrot (SEARS, CEA, Université Paris-Saclay), Y. Gazal, F. Maury, T. Duguet (CIRIMAT, CNRS/INPT/UPS), E. Monsifrot (Dephis), F. Schuster (CEA)

Status of ATF Cladding Development at KAERI

Hyun-Gil Kim, Il-Hyun Kim, Yang-Il Jung, Dong-Jun Park, Jung-Hwan Park, Young-Ho Lee, Byung-Kwon Choi (KAERI)

Advanced Codes and Methodologies Supporting Implementation of Framatome’s Accident Tolerant Fuel in the U.S.A.

F. Curca-Tivig (Framatome GmbH), S. Cole (Framatome Inc.), N. Vioujard (Framatome SAS)

Bison Application to the Analysis of LWR Fuel Responses Under Accident Conditions

Wenfeng Liu, Anh Mai, John Alvis, Joseph Y. R. Rashid (Structural Integrity Associates, Inc.), Charles Folsom, Richard L. Williamson (INL)

Modeling Fuel Assembly Distortion in Light Water Reactors Using Bison

Swetha Veeraraghavan, Albert Casagranda, Benjamin Spencer (INL)

Investigation of Coated Cladding Ballooning Behavior Using Bison

K. A. Gamble (INL)

Modeling of Westinghouse Advanced Fuels EnCore and ADOPT with the CASL Tools

F. Franceschini (Italy Westinghouse Mangiarotti), V. Kucukboyaci, D. Strucker, E. J. Lahoda, Z. Karoutas (Westinghouse)

Overview of R&D Program for Evaluating Spent Nuclear Fuel Integrity Under Normal Conditions of Road and Sea Transport in Korea

Hyeong Koo Kim, Jae Jun Lee, Joong Jin Kim, Seong Ki Lee (KEPCO NF)

Hydride Characterization in Zircaloy-2 Liner Cladding After C-Shaped Ring Compression Tests

Liliana I. Duarte (PSI), Francesco Fagnoni (Aalborg Univ), Robert Zubler, Weijia Gong, Pavel Trtik, Johannes Bertsch (PSI)

First Phase of the Spent Fuel Autoclave Leaching Experiments (SF-ALE) at SCK-CEN

Thierry Mennecart, Gregory Leinders, Christelle Cachoir, Guy Cornelis, Göran Verpoucke (SCK-CEN), Giuseppe Modolo, Dirk Bosbach (FzJ), Karel Lemmens, Marc Verwerft (SCK-CEN)

The Nuclear Fuel Storage Demonstration Project in Taiwan

Wan-June Chiu, Yaw-Hwa Shiu, Che-Chung Tseng (INER)

PROtect SiC: Framatome’s Revolutionary ATF Solution for Improved Performance and Safety in LWRs

K. Nimishakavi (Framatome Inc.), B. Sanders (CORYS), L. Duquesne (Framatome Fuel), C. Lorrette (CEA)

Overview of Westinghouse Lead EnCore Accident Tolerant Fuel Program

Robert Oelrich, Zeses Karoutas, Peng Xu, Javier Romero, Hemant Shah, Jorie Walters, Ed Lahoda, Michael Sivack, John Lyons, Luke Czerniak, Frank Boylan, Raghu ?vali, Andrew Bowman (Westinghouse), Magnus Limbäck, Antoine Claisse, Jonathan Wright (Westinghouse Electric Sweden AB)

Recent Progress in Development of Accident Tolerant FeCrAl-ODS Fuel Claddings for BWRs in Japan

K. Sakamoto, Y. Miura (NFD), S. Ukai (Hokkaido Univ), A. Kimura (Kyoto Univ), A. Yamaji (Waseda Univ), K. Kusagaya (GNF-J), S. Yamashita (JAEA)

Overview of Accident-Tolerant Fuel R&D Program in Japan

S. Yamashita, I. Ioka, Y. Nemoto, T. Kawanishi, M. Kurata, Y. Kaji, T. Fukahori (JAEA), T. Nozawa (National Institutes for Quantum and Radiological Science and Technology), D. Sato (Mitsubishi Nuclear Fuel Co., Ltd.), N. Murakami (Mitsubishi Heavy Industries, Ltd.), H. Sato (Toshiba Energy Systems & Solutions Corp), T. Kondo (GE-Hitachi), K. Sakamoto (NFD), K. Kusagaya (GNF-J), S. Ukai (Hokkaido Univ), A. Kimura (Kyoto Univ), A. Yamaji (Waseda Univ)

Optimized Gap Conductance Model for UO2-Zircaloy Interfaces and Identified Sources of the Uncertainties in the Model

Aysenur Toptan (NCSU), David J. Kropaczek (NCSU, ORNL), Maria N. Avramova (ORNL)

Variance-Based Sensitivity Analysis Approach Applied to Hydrogen Migration and Redistribution Model in Bison

Zineb Aly (Penn State), Albert Casagranda, Giovanni Pastore (INL), Nicholas R. Brown (Univ of Tennessee)

Validating the Fill Gas Thermal Conductivity Models for Gap Conductance Calculations in Nuclear Fuel Performance Codes

Aysenur Toptan (NCSU), David J. Kropaczek (NCSU, ORNL), Maria N. Avramova (ORNL)

Source Range Detector Response Modeling Using VERA

Cole Gentry, Andrew Godfrey, Eva Davidson, Germina Ilas, Benjamin Collins, Shane Hart, Kang-Seog Kim, Tara Pandya, Katherine Royston, Gregory Davidson, Seth Johnson, Thomas Evans (ORNL), Gary Wolfram (PNNL), Scott Palmtag (NCSU)

Influence of Cracking Direction on Fracture Mechanics During DHC of Zircaloy-2 Cladding

A. W. Colldeweih, W. Gong, R. Zubler, J. Bertsch, P. Trtik (PSI)

Evaluation of BWR Spent Fuel Potential for Reconfiguration and Damage During Storage and Transportation Accidents

William F. Lyon, Joe R. Rashid, Anh Mai, Myles T. Parr (Structural Integrity Associates, Inc.)

Leaching Behavior of Nuclides from BWR Spent Fuel and TMI-2 Debris

Takeshi Sonoda, Kenta Inagaki, Takanari Ogata (CRIEPI), Daniel Serrano-Purroy, Vincenzo V. Rondinella (EC-JRC)

OECD/NEA Nuclear Science Fuel Activities Spanning Scales and Technologies

I. Hill, J.-F. Martin, D. Costa, A. Vànyi, S. Cornet, T. Ivanova (OECD/NEA)

Investigation of Corrosion and High Temperature Oxidation of Promising ATF Cladding Materials in the Framework of the Il Trovatore Project

Mirco M. Grosse (KIT), Koba Van Loo (KU Leuven), Erkka L. Frankberg (Italian Inst of Technology), Chongchong Tang (KIT), Konstantza Lambrinou (SCK-CEN), F. Di Fonzo (Italian Inst of Technology), Martin Steinbrück (KIT)

Development Status of High Thermal Conductive UO2 Pellet as ATF at KAERI

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

Round Robin Exercise of the Candidate ATF Cladding Materials Within the ACTOF Project

Martin Ševe?ek, Jakub Krej?í, Adéla Chalupová, Jitka Kabátová, František Manock, Jan Ko?í, Ladislav Cvr?ek (CTU in Prague), Chongchong Tang, Martin Steinbrück, Mirco Grosse (KIT), Sami Penttilä, Juha-Matti Autio, Jari Lydman, Aki Toivonen (VTT Technical Research Centre of Finland), Bo?ena Sartowska, Wojciech Starosta, Lech Wali? (Inst of Nuclear Chemistry and Technology), Zoltan Hózer, Tamás Novotny, Erzsébet Perezné-Feró, Anna Pintér Csordás, M. Horváth, Péter Szabó (Hungarian Academy of Sciences, KFKI Atomic Energy Research Inst), Claudia Giovedi (Univ of São Paulo), Peng Xu (Westinghouse)

Critical Heat Flux and Crud WALT Loop Measurements for Westinghouse Accident Tolerant Fuel

Zeses Karoutas, Guoqiang Wang, William A. Byers (Westinghouse)

Bison as a PCI Screening Tool—PCI Failure Model Development

Joseph Y. R. Rashid, Wenfeng Liu (Structural Integrity Associates, Inc.), Richard L. Williamson (INL)

Locked Rotor Studies to Quantify Benefits of Accident Tolerant Fuel Technologies

Yixing Sung, Serhat Lider, Michael P. Johnson, Zeses E. Karoutas (Westinghouse)

Improvements in CTFFuel for Core Follow Applications in VERA

J. Hu, R. Salko, S. G. Stimpson, A. T. Godfrey, A. Wysocki, B. S. Collins (ORNL)

Effect of Crossflow Modeling on Vapor Void Fraction and Criticality in a BWR Fuel Assembly Using MPACT/CTF

Jacob P. Gorton (Univ of Tennessee, ORNL), Benjamin S. Collins (ORNL), Nicholas R. Brown (Univ of Tennessee)

Inference of Crud Model Parameters from Plant Data

Benjamin Collins, William Gurecky (ORNL), Lindsay Gilkey (SNL), Alicia Elliott, David Kropaczek (ORNL)

Anisotropic Influence of Hydrides on Zircaloy Fatigue

Weijia Gong, Mikael Mille, Robert Zubler, Johannes Bertsch (PSI)

Post-Irradiation Examination of KKB Special Fuel Rods

Joakim K.-H. Karlsson, Anders Puranen, Pia Tejland, Janne Pakarinen, Kyle Johnson, Charlotta Askeljung, Anna-Maria Alvarez (Studsvik Nuclear AB), Arno Benen, Andreas Hüttmann, Sten Lundberg (Vattenfall Europe Nuclear Energy)

Hydride Reorientation and Redistribution Under Non-Uniform Stress

Weijia Gong, Pavel Trtik, Robert Zubler, Johannes Bertsch (PSI)

Destructive Examinations of High Burnup Pressurized Water Reactor Fuel Rods

R. A. Montgomery, R. N. Morris, R. H. Ilgner, J. M. Giaquinto, B. B. Bevard, J. M. Scaglione (ORNL), Tom Brookmire (Dominion Energy)

FeCrAl ATF Safety Benefits for Boiling Water Reactors

Francis Bolger, Guangjun Li, Daniel Pappone (GE-Hitachi)

Initial Valuation of Accident Tolerant Fuel for Industry Adoption: ATF Valuation 1.0

Stephen M. Hess, Jeff Gabor (Jensen Hughes), Aladar Csontos, Nathan Capps (EPRI)

The U.S. Accident Tolerant Fuels Program—A National Initiative Coming of Age

F. J. Goldner, W. McCaughey (DOE), S. L. Hayes, D. M. Wachs (INL), K. A. Terrani, A. T. Nelson (ORNL), K. J. McClellan, C. R. Stanek (LANL)

Valuation of Accident Tolerant Fuel for Industry Adoption: ATF Valuation 2.0

Stephen M. Hess, Jeff Gabor (Jensen Hughes), Aladar Csontos, Nathan Capps (EPRI)

Accident Tolerant Fuel Benefits Analysis for AOOs and DBAs

Nathan Capps (EPRI), Jeff Reed, Brett Boman, Chris Lewis, Nicolas Vioujard (Framatome Inc.), Aladar Csontos (EPRI)

Full-Core Normal and Preliminary Transient Analysis for SiC-Based Rod Designs

Yanan He (MIT, Xi’an Jiaotong Univ), Yangbin Deng (Shenzhen Univ), Koroush Shirvan (MIT)

Economic Benefits of Higher Enriched Assays for 24-Month Cycle Length

Coral Kazaroff, Andrew Johnson, Dan Kotlyar (Georgia Tech), Joshua L. Parker (Framatome Inc.)

Advancements in the Framatome Crud and Corrosion Risk Assessment Process for Pressurized Water Reactors

B. G. Lockamon, S. M. Palzewicz, J. H. Jones, D. S. Tobin (Framatome Inc.)

Radiation Transport Methods to Support Subsequent License Renewal (SLR)

Justin Byard, J. R. Worsham III (Framatome Inc.)

Pin2Perform: A Framework for Consistent Fuel Performance Calculations

Daniel O’Grady, Dean Reid Price, Tomasz Kozlowski (Univ of Illinois), Julie-Fiona Martin, Ian Hill (OECD/NEA)

Demonstration of Bison/TRACE Coupling (CRAB) Through Validation Case LOFT L2-5

Russell Gardner, Cody Permann (INL), Matthew Bernard (NRC), Richard Williamson (INL)

Development of Evaluation Methodology of Core-Wide Fuel Rod Burst in LOCA Safety Analysis

Joosuk Lee, Young-Seok Bang (KINS)

Monte Carlo Analysis of Cladding Burst During LOCA Using Bison

Cole Blakely, David Kamerman, Charles Folsom, Kyle Gamble (INL)

Safety Assessment of UN/Zr Fuel with SiC Cladding Under Large Break Loss-of-Coolant Accident

Libo Qian, Hongxing Yu, Yufa Sun, Jian Deng, Dan Wu, Shuhua Ding, Wei Chen, Zhongchun Li, Xi Chen, Lili Liu (Nuclear Power Inst of China)

Investigation of Zr-Based Alloy Cladding Burst Mechanisms Under Station Blackout Using Bison

Jianguo Yu, Cole Blakely, Hongbin Zhang (INL)

Immersion Testing of FeCrAl Tubes Under Simulated Light Water Nuclear Reactor Normal Operation Conditions

Raul B. Rebak, Timothy B. Jurewicz, Michael Larsen (GE Research), Kan Sakamoto (NFD)

Analysis of FeCrAl-ODS Cladded Fuel Performance During BWR Power Ramp with FEMAXI-7

Yoshihiro Fujiwara, Akifumi Yamaji (Waseda Univ), Shigeharu Ukai (Hokkaido Univ), Kan Sakamoto (NFD), Shinichiro Yamashita (JAEA)

Effect of Yttrium Addition on the Corrosion Behavior of FeCrAl Alloys in Simulated Primary Water Condition

Taeyong Kim, Seung Chang Yoo, Inyoung Song, Junhyuk Ham, Yunju Lee (UNIST), Sungyu Kim, Chi Bum Bahn (Pusan National Univ), Ji Hyun Kim (UNIST)

Length Dependence of FeCrAl Accident-Tolerant Fuel Cladding Under Simulated Loss-of-Coolant Accident Testing

B. Garrison, M. Howell, M. N. Cinbiz, K. Linton, M. N. Gussev (ORNL)

Separate-Effects Validation Experiments for Models of Fracture in Ceramic Nuclear Fuel

Benjamin W. Spencer, Nicholas E. Woolstenhulme, Leigh A. Emerson, Ju-Yuan Yeh, D. Devin Imholte, Connie M. Hill, Daniel B. Chapman, Colby B. Jensen (INL), Mary Lou Dunzik-Gougar (Idaho State Univ), Travis W. Knight, Theodore M. Besmann, Sobhan Patnaik (Univ of South Carolina), Sean M. McDeavitt, Luis Ortega, Delia Perez-Nunez (Texas A&M), Heng Ban (Univ of Pittsburgh)

Implementation of Chromia-Doped Fuel in RODEX4 and Downstream Codes and Methods for U.S. BWR Applications

V. I. Arimescu, T. Davis, V. Korolev, M. Anderson (Framatome Inc.), C. Delafoy (Framatome SAS)

Transient MOX Fuel Swelling in TESPA-ROD Code Applied on CABRI RIA Tests

Felix Boldt (GRS GmbH, Technical Univ of Munich), Heinz-Günther Sonnenburg (GRS GmbH)

Transient Boiling During RIA: Out-of-Pile Testing and In-Pile Design for TREAT

Kevin Terrill, Richard Christensen (Univ of Idaho), Colby B. Jensen, Charles Folsom (INL)

Behavior of LWR Fuels with Additives Under Reactivity-Initiated Accident Conditions

Takeshi Mihara, Yutaka Udagawa, Masaki Amaya, Yoshinori Taniguchi, Kazuo Kakiuchi (JAEA)

Behavior of High-Burnup LWR-MOX Fuel Under a Reactivity-Initiated Accident Condition

Yoshinori Taniguchi, Yutaka Udagawa, Takeshi Mihara, Masaki Amaya, Kazuo Kakiuchi (JAEA)

Testing Accident Tolerant Fuels in Reactivity Initiated Accident Conditions

D. W. Kamerman, D. D. Imholte, N. E. Woolstenhulme, C. B. Jensen, D. M. Wachs (INL)

Estimation Source Term with Time and Reference Spent Fuel in Korea

Ara Go, Daesik Yook (KINS), GunHee Jung, YeSeul Cho, Ser Gi Hong (Kyung Hee Univ)

A Study on Thermal Behavior for the OASIS (Optimized and Safe Interim Storage System)-32D Spent Nuclear Fuel Cask

Kunwoo Yi, Kyongin Ju, Seongchan Park (KEPCO Eng and Construction Co., Inc.)

Thermal Hydraulic CFD Simulations and Experimental Investigation of Deformed Fuel Assemblies

Anthony Chang (Orano), Tom Reeves, R. Brian Jackson (TerraPower)

Using TRACE and FRAPTRAN Codes to Simulate and Analyze the Severe Accident and Ultimate Response Guideline of Maanshan Nuclear Power Plant

Bo-Ru Shen, Tsung-I Shen, Shao-Wen Chen, Jong-Rong Wang, Chunkuan Shih, Jung-Hua Yang (National Tsing Hua Univ)

Preliminary Design of I-Loops in ATR for Irradiation Testing of LWR Fuels

N. S. Oldham, N. E. Woolstenhulme, K. R. Horman, J. L. Peterson-Droogh, T. L. Maddock, D. M. Wachs (INL)

Severe Accident Analysis of MELCOR2.2/SNAP for Maanshan Nuclear Power Plant ELAP Event

Wei-Yuan Cheng, Shang-Chih Lin (National Tsing Hua Univ), Jong-Rong Wang (Nuclear and New Energy Education and Research Foundation), Shao-Wen Chen (National Tsing Hua Univ), Chunkuan Shih (Nuclear and New Energy Education and Research Foundation)

Oxidation of Zirconium Cladding in Air, Nitrogen, and Nitrogen-Rich Steam Atmospheres

Erzsébet Perez-Feró, Anna Pintér-Csordás, Tamás Novotny, Zoltán Hózer, Levente Illés, György Zoltán Radnóczi (Hungarian Academy of Sciences)

High Temperature Oxidation Behavior of Fe20Cr2Si Alloy in Steam Environment

Joonho Moon, Sungyu Kim (Pusan National Univ), Ji Hyun Kim (UNIST), Michael P. Short (MIT), Chi Bum Bahn (Pusan National Univ)

Effects of Yttrium on High Temperature Steam Oxidation Behavior of FeCrAl-Y Alloy

Sungyu Kim, Joonho Moon, Chi Bum Bahn (Pusan National Univ)

Cesium Retention Ability in Silica-Based Cesium Compounds

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

High-Temperature Oxidation Behavior of Defected Coating Layer for Accident-Tolerant Fuel Cladding

Y.-H. Lee, J.-H. Park, I.-H. Kim, D.-J. Park, Y.-I. Jung, B.-K. Choi, H.-G. Kim (KAERI)

Preliminary Evaluation of FeCrAl-UN Fuel Rod Performance

Shixin Gao (Science and Technology on Reactor System Design Technology Laboratory), Zhengang Duan (Nuclear Power Inst of China), Yi Zhou, Ping Chen, Liang He, Shichao Liu, Kun Zhang, Xi Qiu (Science and Technology on Reactor System Design Technology Laboratory), Ruiqian Zhang (Nuclear Power Inst of China)

Modeling of the U3Si2/SiC Fuel System Behavior for a RIA Scenario

C. Cozzo, R. Ngayam-Happy, J.-C. Chen, M. Pecchia (PSI), G. Girardin (Kernkraftwerk Gösgen-Däniken AG)

Cause Analysis of Stress Corrosion Cracking Incident due to Polyvinyl Chloride Cable on Glove Box

Yoshikazu Yamada, Kimikazu Shibanuma (JAEA)

Microstructure Characterization of Atomized Dispersion Targets for Mo-99 Production

Tae Won Cho, Ki Nam Kim, Yong Jin Jeong, Kyuhong Lee, Sunghwan Kim, Jong Man Park (KAERI)

High Temperature Steam Oxidation of Cr-Coated SiCf/SiC Composite for LWR Cladding Applications

Jo Jo Lee, Takaaki Koyanagi, Bruce A. Pint, Yutai Katoh (ORNL)

Oxidation of Silicon Carbide in Steam Studied by Laser Heating

H. V. Pham, Y. Nagae, M. Kurata (JAEA), K. Furumoto (Mitsubishi Nuclear Fuel Co., Ltd.), H. Sato (Toshiba Energy Systems & Solutions Corp), R. Ishibashi (GE-Hitachi), S. Yamashita (JAEA)

Assessment of Pre-Irradiation SiC CMC Joint Performance in Representative Cladding Geometries

S. Gonderman, G. Jacobson (General Atomics), T. Koyanagi, C. Petrie (ORNL), C. Deck (General Atomics)

Cycle Specific Evaluation of the Margin to Ballooning and Burst of High Burnup Fuel Rods During a Large Break Loss-of-Coolant Accident

M. Hemlin (Vattenfall Nuclear Fuel), H. Nylén (Ringhals AB)

Computational Studies of Amorphous UO2 for Grain Boundary Behavior

Ember L. Sikorski (Boise State Univ, Center for Advanced Energy Studies), Eric B. Nelson (Boise State Univ), Simon C. Middleburgh (Bangor Univ), Lan Li (Boise State Univ)

Fuel Performance Analysis of Uranium Silicide Fuel for LWRs During Cladding Failure

R. T. Sweet (Univ of Tennessee Knoxville), A. T. Nelson (ORNL), B. D. Wirth (Univ of Tennessee Knoxville, ORNL)

Modeling of Base Irradiation Histories of LOCA Tests Using CMS5 and ENIGMA

Gerardo Grandi (Studsvik Scandpower), Joakim Karlsson (Studsvik Nuclear AB), Mattias Hemlin (Vattenfall Nuclear Fuel)

Fuel Fragmentation During LOCA Simulated Transients: Investigation of Irradiated MOX vs. UO2 Fuel

B. Baurens, C. Esnoul, N. Waeckel, R. Largenton, F. Rossillon, E. Pouillier, J. J. Vermoyal (EdF)

Deformation Behavior of Zircaloy-4 Cladding in a Spent Fuel Pool Accident

Kinya Nakamura, Kenta Inagaki, Takeshi Sonoda, Satoshi Nishimura (CRIEPI)

Determination of Zirconium Oxide Chemistry Through Complimentary Characterization Techniques

Corey M. Efaw, Michael Reynolds (Boise State Univ), Jordan L. Vandegrift, Kassiopeia Smith, Yaqiao Wu, Brian J. Jaques (Boise State Univ, Center for Advanced Energy Studies), Hongqiang Hu (INL), Claire Xiong, Michael F. Hurley (Boise State Univ)

PWR Spent Fuel Rod Burst Research Under Spent Fuel Pool Boiling-Off Accident

Kai He, Zifan Song, Yuntao Zheng, Xiaochuan Jiang, Siyang Zhu, Teng Shen, Xiaodong Huo (China Nuclear Power Eng Co., Ltd.)

Creep-Fatigue Interaction of an Advanced Austenitic Stainless Steel (Alloy 709)

Zeinab Y. Alsmadi, Abdullah S. Alomari (NCSU), N. Kumar (Univ of Alabama), K. L. Murty (NCSU)

Thermal Annealing of Irradiated Prehydrided Zircaloy-4 Materials

Scott C. Middlemas (INL), Daniel Jädernäs (Studsvik), Erik Mader (EPRI)

Joining Technology with Corrosion-Resistant Coating for Silicon-Carbide Fuel Cladding

R. Ishibashi, M. Kida, M. Shibata, T. Kondo (GE-Hitachi), S. Yamashita, T. Fukahori (JAEA)

Development of Additive Manufacturing at Westinghouse

William Cleary, Artem Aleshin, David Huegel, Jason Moore, Thomas Pomorski (Westinghouse)

Applicability of 3D Printing to Manufacture Spacer Grid in Nuclear Fuel

Chaeyoung Nam, Jooyoung Ryu, Joongjin Kim, Namgyu Park, Seungjae Lee (KEPCO NF)

Determination of Hidden Extrapolations via Gaussian Mixture Models

Ross Pivovar (BWXT)

Prediction of Boiling Crisis in a Full-Size Rod Bundle with Spacer Grids

Quan Li, Yuanming Li (Nuclear Power Inst of China), M. Avramova (NCSU), Yongzhong Huang, Zhenhai Liu, Chao Ma, Feipeng Qi, Bo Zhao (Nuclear Power Inst of China)

A Robust Mechanistic Approach to Prediction of Departure from Nucleate Boiling

Xingang Zhao, Koroush Shirvan (MIT), Robert K. Salko (ORNL)

Validation of a Pin-Based Screening Methodology for the Investigation of Pellet-Clad Interaction During Load-Follow Operation

Daniel O’Grady, Tomasz Kozlowski (Univ of Illinois)

Analysis of MM Space for LWR AI Fuel Design Optimization with CMM

Albert Gu (AREVA NP, retired), Guobin Jia (Shanghai Inst of Applied Physics)

Chromium-Coated Cladding Effects in the Context of 10 CFR 50.46c

Michael A. Shockling, Jun Liao, Jeffrey R. Kobelak (Westinghouse)

Modeling and Simulation Strategy for TREAT Experiments

C. P. Folsom, C. B. Jensen, N. E. Woolstenhulme, D. W. Kamerman, D. M. Wachs (INL)

Development of Out of Pile Test for SiC Cladding to Simulate DBA Conditions in PWRs

K. Furumoto, D. Sato, S. Watanabe (Mitsubishi Nuclear Fuel Co., Ltd.), T. Yumura, M. Okamoto (Mitsubishi Heavy Industries, Ltd.), S. Yamashita, T. Fukahori (JAEA)

Recent Advances in Water-Environment Irradiation Testing for Transient and Safety Research at INL

N. E. Woolstenhulme, C. B. Jensen, D. W. Kamerman, T. L. Maddock, N. S. Oldham, D. M. Wachs, S. L. Hayes (INL)

Oxidation Behavior of Zr-Alloy Cladding Candidates for the TREAT Reactor

Jordan L. Vandegrift (Boise State Univ, Center for Advanced Energy Studies), Corey M. Efaw (Boise State Univ), Patrick M. Price (Boise State Univ, Center for Advanced Energy Studies, SNL), Clemente J. Parga (Center for Advanced Energy Studies, INL), Darryl P. Butt (Boise State Univ, Center for Advanced Energy Studies, Univ of Utah), Ben Coryell (INL), Michael F. Hurley (Boise State Univ), Brian J. Jaques (Boise State Univ, Center for Advanced Energy Studies)

Oxidation and Quench Behavior of Cold Spraying Cr-Coated Zircaloy Fuel Cladding Under Severe Accident Scenarios

Chongchong Tang, Mirco Grosse, Martin Steinbrueck (KIT), Koroush Shirvan (MIT)

Fabrication, Characterization, and Testing of Cr-Coated Zr Alloy Nuclear Fuel Rod Cladding for Enhanced Accident Tolerance

A. K. Evans, P. J. Kelly (MMU), D. T. Goddard (NNL), A. Cole-Baker (Wood plc), G. Obasi, M. Preuss (Manchester Univ), E. P. Vernon (NNL)

Experimental Investigation of Cold-Spray Cr-Coated Cladding During Normal and Accident Conditions

Koroush Shirvan, Arunkumar Seshadri, Akshay Dave, Bren Philips (MIT), Martin Ševe?ek (CTU in Prague, Alvel a.s.), Jakub Krej?í, Adéla Chalupová (CTU in Prague, UPJ Praha a.s.), Miltiadis Kennas, Ekaterina Ryabikovskaya, Aaron French, Hyosim Kim, Lin Shao (Texas A&M)

BWR Water Chemistry Trends and Impacts on Fuel Performance

Aylin Kucuk, Michelle Mura (EPRI), Rob Schneider, Dan Lutz (GNF-Americas), Britta Helmersson, Lena Oliver (Westinghouse Electric Sweden AB), Brian Lockamon (Framatome Inc.)

Enhanced Efficiency and Systematic Risk Assessment at Edwin I. Hatch Nuclear Plant—GNF3 Fuel Introduction

R. Dunavant, J. Chavers, A. Phillippe, T. Collart, D. Arvan, R. Patrick, D. Carvallo, R. Fennel (Southern Nuclear), P. McCumbee, F. Bolger, J. Ingraham (GE-Hitachi)

Mitigating the Effects of Baffle-Related Wear in Babcock and Wilcox Nuclear Power Reactors

G. F. Borum, S. M. Mazurkiewicz (Framatome Inc.), D. L. Smith (Entergy Corp)

Experimental Behavior of Chromium-Based PVD Coated Cladding Materials During LOCA Transient

Jakub Krej?í (UJP PRAHA a.s.), Adéla Chalupová, Ladislav Cvr?ek, Martin Ševe?ek (CTU in Prague), Vojt?ch Rozkošný (UJP PRAHA a.s.), Patricie Halodová, Petra Gávelová (Research Centre Rez)

Behavior of High-Burnup Advanced LWR Fuel Cladding Tubes Under LOCA Conditions

Takafumi Narukawa, Masaki Amaya (JAEA)

Results of the Bundle Test QUENCH-19 with FeCrAl Claddings

J. Stuckert, M. Grosse, M. Steinbrueck (KIT), K. Terrani (ORNL)

Hydrides in Irradiated Liner Cladding—Local and In-Depth Concentration Determination by Neutron Radiography

Liliana I. Duarte (PSI), Francesco Fagnoni (Aalborg Univ), Robert Zubler, Weijia Gong, Pavel Trtik, Johannes Bertsch (PSI)

OpenFOAM Thermal Analysis of Nuclear Thermal Propulsion Fuel and Moderating Elements

J. C. Wang, D. Kotlyar (Georgia Tech)

The SIF Model of Zr-4 Cladding Tube with Axial Cracks

L. Chen, L. L. Liu, X. M. Song, H. Pang, X. M. Xie (Nuclear Power Inst of China), X. G. Zeng (Sichuan Univ)

Addressing the Negative Industry Trend of Debris-Related Failures in Commercial Nuclear Fuel

S. M. Mazurkiewicz (Framatome Inc.), C. Bretting (Framatome GmbH), C. Petit (Framatome SAS)

GNF Fuel Reliability and Channel Performance: 2019 Update

R. Schneider, D. Lutz, P. McCumbee, P. Cantonwine (GNF-Americas)

Advanced Debris Protection for PWR Fuel

Michael E. Conner, Yuriy Aleshin, Robert A. Brewster, Caroline K. Duncan (Westinghouse)

Development and Testing of BWR Fuel Debris Filter

Uffe Bergmann, Fredrik Waldemarsson (Westinghouse Electric Sweden AB)

Framatome Shielding Fuel Assemblies Ensure Plant Lifetime Extension

Lars Ackermann, Christian Möllmer, Jörg Peucker, Dominik Streit (Framatome GmbH), Jenny Roudén, Henrik Nylén (Ringhals AB), Malin Löwe, David Schrire (Vattenfall Nuclear Fuel)

Irradiation of Advanced Neutron Absorbing Material to Support Accident Tolerant Fuel Applications

J. N. Stevens, M. Aumand (Framatome Inc.), B. Winterholer, G. Raveu (Framatome), A. Le Coq, N. Cetiner, K. Linton (ORNL)

Burnup Performance Analysis for Candidate Materials of the LWR Accident Tolerant Control Rod

Yong Liu, Mancang Li, Yingrui Yu, Peng Xiao, Xingbo Wang, Bin Zhang, Dongyong Wang (Nuclear Power Inst of China)

Thermal and Neutronic Analysis for Irradiation of Advanced Neutron- Absorbing Material in the High Flux Isotope Reactor

N. O. Cetiner, J. R. Burns, A. G. Le Coq, K. D. Linton, C. M. Petrie (ORNL), J. N. Stevens (Framatome Inc.), B. Winterholer, G. Raveu (Framatome)

Evolution of SSTC NRS Computer Models for Carrying Out Independent Verifying Evaluation of the Mixed Cores at the Ukrainian NPPs

M. Ieremenko, I. Ovdiienko, O. Dybach, I. Shevchenko (State Scientific and Technical Center for Nuclear and Radiation Safety), A. Shepitchak (State Nuclear Regulatory Inspectorate of Ukraine)

Reactivity Initiated Accident Multi-Physics Simulation and Output Data Compression

Alexey Cherezov, Hanjoo Kim, Jinsu Park, Deokjung Lee (UNIST)

Hatch TRACG ECCS LOCA Application

R. Dunavant, J. Chavers (Southern Nuclear), M. Holmes, G. J. Li, J. Fricano, R. Harrington (GE-Hitachi)

Fuel Performance Uncertainty due to Manufacturing Tolerances

Jinan Yang, Benjamin Collins, Shane Stimpson (ORNL)

Benchmark of Fuel Performance Codes for FeCrAl Cladding Behavior Analysis

G. Pastore, K. A. Gamble (INL), M. Cherubini (Nuclear and Industrial Engineering), C. Giovedi (Univ of São Paulo), A. Marino (National Atomic Energy Commission), A. Yamaji (Waseda Univ), Y. Kaji (JAEA), P. Van Uffelen (EC-JRC), M. S. Veshchunov (IAEA)

Irradiation Growth Behavior of Improved Zr-Based Alloys for Fuel Cladding

Masaki Amaya, Kazuo Kakiuchi, Takeshi Mihara (JAEA)

Nuclear Power Plant Flexible Operation

J. Plancher, A. Grossetete (Framatome), S. Nguyen (EdF)

Safer and Faster Outages with Modern Prediction Tools

Veit Marx, Markus Singer (Framatome GmbH), Kai Fülber (PreussenElektra GmbH)

Effect of Alloying Elements on Formation and Stability of Dislocation Loops in Zirconium

M. Christensen, W. Wolf, C. Freeman, E. Wimmer (Materials Design, Inc.), R. B. Adamson (Zircology Plus), M. Griffiths (Advanced Nuclear Technology), E. V. Mader (EPRI)

Nano-Grained UO2 Grain Growth Kinetics at 600-800°C: An In-Situ Synchrotron X-Ray Study

K. Mo, Y. Miao (ANL), T. Yao, J. Lian (RPI), J.-S. Park, J. Almer, S. Bhattacharya, A. M. Yacout (ANL)

Characterization of (U,La)O2 Fuel from the Standpoint of Power Reactor Applications

E. N. Onder, A. Bergeron, L. Fu, J. Mouris, D. Roubtsov, M. Saoudi (CNL)

Improving the Fuel Qualification Process Through the Use of Microscale Samples for Describing Bulk Material Properties

Daniel LaBrier (Idaho State Univ), Jason Schulthess (INL), Wade Marcum (Oregon State Univ), Mitchell K. Meyer (INL, Oregon State Univ)

Sintering and FEA Simulation of Oxide Fuel Pellet Containing Lumped Gd2O3

Qusai M. Mistarihi, Faris Sweidan, Jang Soo Oh, Yonghee Kim, Ho Jin Ryu (KAIST)

Grid Width Growth Behaviors in Korean PWR Nuclear Fuels

Y. K. Jang, J. W. Kim, J. S. Yoo (KEPCO NF)

Introduction of the Temelin Irradiated Cladding Project—TIRCLAD 1

Martin Ševe?ek (CTU in Prague, Alvel a.s.), Josef B?lá?, Stanislav Linhart, Radomír ?ehá?ek (Alvel a.s.), Martina Malá, Ond?ej Srba (Research Center Rez)

GAIA Fuel Implementation in the U.S.

Scott D’Orio, Robert Clarke (Framatome Inc.), Scott Thomas (Duke Energy)

Westinghouse CE16NGF Fuel Assembly Performance

M. Dye, M. O’Cain (Westinghouse)

ATRIUM 11 Global Implementation

Norman Garner, Steven Cole (Framatome Inc.), Nico Vollmer, Robert Koch (Framatome GmbH

Towards Industrial-Scale Manufacture of UN Fuel for Water-Cooled Reactors

Janne Wallenius (LeadCold Reactors), Mikael Jolkkonen, Yulia Mishchenko (KTH), Daniel Laurin (Promation Nuclear)

Improved Hydrothermal Corrosion Resistance of UN Fuel Forms via Addition of Metallic Constituents

Jennifer K. Watkins (Boise State Univ, Center for Advanced Energy Studies), Ember Sikorski, Lan Li (Boise State Univ), Brian J. Jaques (Boise State Univ, Center for Advanced Energy Studies)

Development of Self-Healing Coating on Fuel Cladding for Water-Cooling Nuclear Reactors

Z. G. Duan, G. S. Xin, Y. Zhou, Y. M. Li (Nuclear Power Inst of China), H. Abe, H. L. Yang, S. Kano, J. McGrady (Univ of Tokyo)

Validation and Verification of the FINIX Fuel Behavior Module

Jussi Peltonen, Henri Loukusa, Ville Tulkki (VTT Technical Research Centre of Finland)

Coupling Methodology for the Multidimensional Fuel Performance Code OFFBEAT and the Monte Carlo Neutron Transport Code Serpent

Alessandro Scolaro (EPFL), Yves Robert (Inst National des Sciences Appliquées Lyon, EPFL), Carlo Fiorina (EPFL), Ivor Clifford (PSI), Andreas Pautz (EPFL)

Framatome Advanced Codes and Methods Application to Control Rod Ejection, Single Rod Withdrawal, and Steam Line Break at Power

Ruxandra Bobolea, William Walters, Keith Maupin, Richard Deveney, Tim Lindquist, Robert Barner (Framatome Inc.)

Towards Understanding Thermal Cycling Effects on Hydride Precipitation and Dissolution in Zirconium Alloys and Subsequent Effect on Cladding Performance

A. Cole-Baker, P. Binks, J. R. Lovett, H. Hulme, M. Gass (Wood plc)

A Study on Corrosion Behavior of Zirconium Alloy at High Temperature Water Condition Under UV Irradiation

Taeho Kim, Zefeng Yu, Yalong He, Mohamed Elbakhshwan, Li He, Adrien Couet (Univ of Wisconsin Madison)

BWR Water Chemistry Transients and Crud-Induced Corrosion Fuel Failure Risk Assessment

Aylin Kucuk (EPRI), Roy Nelson (Energy Northwest), Alfredo Avila (Comision Federal de Electricidad), Kornelia Szwarc (Entergy Nuclear Northeast), Kenny Epperson (Epperson Engineering), Gerald A. Potts, Joe Giannelli (Structural Integrity Associates), Garry Gose (Zachry Nuclear)

Oxide Surface Peeling (OSP) of Advanced Zirconium Cladding Irradiated in PWRs

G. Pan, D. Mitchell, A. Atwood, J. Iyer (Westinghouse), M. Limbäck, L. Fridemo (Westinghouse Electric Sweden AB), L. Cai (Westinghouse), C. Muñoz-Reja, A. Muñoz (ENUSA)