Global 2019

Author Index

Full Issue

Noble Gas Separation Using Metal Organic Frameworks at Low Temperature

Praveen K. Thallapally, Jian Liu, Michael A. Sinnwell, Radha K. Motkuri (PNNL), invited

Capture of Iodine in Off-Gas Streams from Aqueous Used Nuclear Fuel Reprocessing—Deep Bed Test Results

Nick Soelberg, Amy K. Welty, Sam Thomas (INL)

Overview of French R&D on SFR MOX Fuel Fabrication

F. Mazaudier, P. Dubuisson (CEA)

A New Photochemical Reactor for the Rapid Reduction of U(VI) in the Development of Mixed Metal Oxide Fuel Production Processes

Michael A. Bromley, Colin Boxall (Lancaster Univ), Robin Taylor, Mark Sarsfield (NNL)

Study on the Synthesis of Amidoximized Polyacrylonitrile and Its Adsorption to Uranyl Ion

Heng Jiang, Fuqiu Ma, Peng Liu, Yunyang Gui, Meng Cao, Chen Guo, Xinwei Li (Harbin Engineering Univ)

Verification of Detailed Core-Bowing Analysis Code ARKAS_Cellule with IAEA Benchmark Problems

Hirokazu Ohta (CRIEPI), Kazuya Ohgama, Hidemasa Yamano (JAEA)

Evaluation and Analysis of Assembly Bowing Reactivity Coefficients in AFR-100 with the RAINBOW Code

T. Jing (INL), W. S. Yang, P. Deng (Univ of Michigan), T. K. Kim (ANL)

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (5) Validation of a Multi-Phase Model for Eutectic Reaction Between Molten Stainless Steel and B4C

Xiaoxing Liu, Koji Morita (Kyushu Univ), Hidemasa Yamano (JAEA)

Proven Safe and Effective Process for the Treatment of Bulk Sodium at Shutdown Reactors and Research Facilities

Anthony Chang (Orano Federal Services, LLC), Dominique Villani (Framatome)

DEM&MELT In-Can Vitrification Process for D&D and Remediation Waste

Régis Didierlaurent (Orano), Isabelle Hugon, Jean-François Hollebecque (CEA), Thierry Prevost (Orano), Hubert-Alexandre Turc (CEA), Guillaume Lecomte (ECM Technologies), Stéphane Catherin (ANDRA), Kohei Shibata (ANADEC)

Stabilization Processing of Hazardous and Radioactive Liquid Wastes Derived from Advanced Aqueous Separation Experiments for Safety Handling and Management of Waste

Masaumi Nakahara, Sou Watanabe (JAEA), Hiromichi Ogi (Inspection Development Co. Ltd.), Yoichi Arai, Haruka Aihara, Risa Motoyama, Atsuhiro Shibata, Kazunori Nomura (JAEA), Akihiko Kajinami (Kobe Univ)

Electrochemical Behaviors of Nb in the LiCl-KCl Molten Salt

Gwan Yoon Jeong (UNIST), Sungjune Sohn (KAERI), Younghwan Jeon, Jaeyeong Park, (UNIST)

Removal of Bond Sodium from an Irradiated Full-Length Experimental Breeder Reactor—II Blanket Element via Melt-Drain-Evaporate Process

S. D. Herrmann, D. L. Wahlquist, J. C. Price, M. N. Patterson (INL)

Ongoing NEA Scientific Activities Related to Advanced Fuel Cycles

S. Cornet (NEA), N. Chauvin (CEA), D. Costa, T. Ivanova (NEA)

The GIF Webinar Initiative: Past, Present and Future

Patricia Paviet (PNNL)

Selective Separation of Am(III) from PUREX Raffinate with a TODGA-Based Solvent Using Innovative Hydrophilic Complexing Agents

Giuseppe Modolo, Andreas Wilden, Peter Kaufholz (FzJ), Cécile Marie, Vincent Vanel, Manuel Miguiriditchian, Stéphane Bourg (CEA), Alessandro Casnati (Univ delgi Studi di Parma), Andreas Geist (KIT)

Extraction Behavior of Lanthanides from Nitric Acid Medium with N,N’-Dimethyl-N,N’-Dioctyl-3-Oxadiglcolamide

Yang Gao, Zhi Zhang, Caishan Jiao, Yu Zhou, Meng Zhang, Hongguo Hou (Harbin Eng Univ), Guoxin Tian (Harbin Eng Univ/China Inst of Atomic Energy)

Behavior of Lanthanides and Actinides for Their Mutual Separation Using Extractant and Masking Agent

Yuji Sasaki, Keisuke Morita (JAEA), Masahiko Matsumiya (Yokohama National Univ), Masahiko Nakase (Tokyo Inst Technology)

Extraction Separation of Minor Actinides and Lanthanides by 1,10-Phenanthroline-2,9-Diamide with Phenyl Group in Nitric Acid Systems

Nao Tsutsui (Tokyo Inst of Technology/JAEA), Masahiko Nakase, Sayumi Ito (Tokyo Inst of Technology), Yasutoshi Ban, Tatsuro Matsumura (JAEA), Kenji Takeshita (Tokyo Inst of Technology)

Sulfonamide Ligands for Extraction of Ln(III) and An(III) from Alkaline Aqueous Media

Evgen V. Govor, Oluwaseun W. Adedoyin, Alexander N. Morozov, April A. Rains, B. Nabi Ajoff, Alexander M. Mebel, Konstantinos Kavallieratos (Florida International Univ)

Flowsheet Development for the Dissolution of Aluminum-Clad Research Reactor Fuels in the Savannah River Site H-Canyon Facility

Tracy S. Rudisill, William E. Daniel, Philip M. Almond (SRNL)

Spent Nuclear Fuel RD&D Experience, Accomplishments, and Capability at ORNL

E. D. Collins, D. E. Benker, F. R. Chattin, L. K. Felker, F. R. Chattin, P. D. Bailey, R. J. Vedder, G. D. Del Cul, B. B. Spencer, R. T. Jubin, (ORNL)

Advances on the Treatment of Research Reactor Used Fuels at La Hague

Paul Murray, Sven O. Bader (Orano)

Analysis of Water Absorption onto CERLA and THORIA Thin Films by Direct Mass and Contact Angle Measurements

D. Laventine, C. Boxall, M. Chombakkadath (Univ of Lancaster), R. Orr, R. Taylor (NNL)

Exchange of the Rotary Dissolver Wheel at La Hague R1 Facility: An Exceptional Maintenance Operation

S. Gaiffe, C. Schultz, F. Lepresle, Ph. Guibert, D. Leveel, H. Leberbanchon, Ph. Morin, P. Boudaud, C. Fauque, A. Coudray, C. Veyer (Orano)

Using Past Experience to Tackle Today’s Challenges in Generation IV Fast Reactor Technologies

J. Lillington, J. Lavarenne, B. Lindley (Wood)

Lessons Learned from Fast Flux Test Facility Experience in Containment Design and Sodium Fire Testing

D. W. Wootan, R. P. Omberg (PNNL), T. M. Burke (Westinghouse Hanford Co. (Retired)), C. Grandy (ANL)

A Modern Transmutation Library Database of Nuclear Fuel Cycle Reactor Stage Performance Information

Mark E. Ambrose, Adrian M. Leandro (Penn State), Jin Whan Bae, Joshua L. Peterson-Droogh (ORNL), Michael Todosow (BNL), Nicholas R. Brown (Univ of Tennessee, Knoxville)

A First Approach to Resilience of Nuclear Fuel Cycle Scenarios

Weifeng Zhou, Guillaume Krivtchik, Patrick Blaise (CEA)

Technology Characteristics of Transitions to Solid-Fueled and Molten-Salt Fast Reactor Fleets

E. Hoffman, B. Feng (ANL), B. Betzler, E. Davidson, A. Worrall (ORNL)

Fast Reactor Design for Using Low-Enriched Uranium Startup and Transition

E. Hoffman, T. Fei (ANL)

Analysis of Transition Scenario from a PWR to a SFR Fleet Simulated with the CLASS Code

Léa Tillard, Jean-Baptiste Clavel (IRSN), Xavier Doligez (IPNO, CNRS-IN2P3), Éric Dumonteil (IRSN), Marc Ernoult, Jiali Liang (IPNO, CNRS-IN2P3), Nicolas Thiollière (SUBATECH)

Prospective Inventory of Radioactive Materials and Waste Produced by the French Nuclear Fleet According to Various Options

C. Chabert, E. Touron, A. Saturnin, G. Krivtchik, G. Martin, Ph. Miranda, F. Courtin, J. L. Girotto, G. Mathonniere, S. Gabriel, R. Eschbach, A. Allou, R. Boccaccio, F. X. Giffard, A. Bonin, P. Casoli (CEA), F. Laugier (EdF), B. Carlier (Framatome), G. Senentz (Orano)

Development of Separation Technology of Radionuclide in Waste Salt

Geun Il Park, Hwan-Seo Park, Jung Hoon Choi, Ki-Rak Lee, Seung-Youb Han, Jin-Mok Hur (KAERI)

In-Situ Spectroscopy of Lanthanide Chlorides in LiCl-KCl System for Pyroprocessing Applications

Ruchi Gakhar, William Phillips, Steven M. Frank (INL)

Evaluation of Economic Performance Metrics for Nuclear Power Plant Concepts Based on Small and Medium-Sized Reactor Modules and a Large Nuclear Reactor

A. A. Andrianov, I. S. Kuptsov, T. A. Osipova, T. A. Frolova, T. V. Utyanskaya (National Research Nuclear Univ MEPhI), O. N. Andrianova (JSC SSC RF)

Considerations in Radioactive Waste Management for SMRs—The Role of the IAEA

Ian Gordon, Stefano Monti (IAEA)

Three-Dimensional Analysis of Passive Frequency Control in a Soluble-Boron-Free SMR ATOM

Ahmed Amin E. Abdelhameed, Xuan Ha Nguyen, Yonghee Kim (KAIST)

Physics Study for Design Optimization of the Soluble-Boron-Free Small Modular Reactor ATOM

Xuan Ha Nguyen, Seongdong Jang, Yonghee Kim (KAIST)

Feasibility Study on Oxide/Molten Salt-Fueled CANDU Reactor with Two Regions Bundles

Hiroki Ishida, Naoyuki Takaki (Tokyo City Univ)

Proliferation and Terrorism Issues Related to Noble Gas Management at Molten Salt Reactors

Edwin Lyman (UCS)

Progress in Experimental Development of MSR Fuel Cycle Technology

Jan Uhli? (Research Centre Rez), Martin Straka (UJV ?ež), Martin Mare?ek (Research Centre Rez), Lórant Szatmáry (UJV ?ež)

SALIENT-03: Irradiation of Molten Salt Fuel in Ni-Based Alloy Capsules at the High Flux Reactor

E. D’Agata (EC JRC), P. R Hania (NRG), O. Benes, R. Konings (EC JRC), K. Kottrup (NRG), P. Soucek (EC JRC), D. A. Boomstra, P. J. Baas, F. F Charpin-Jacobs, H. J. Uitslag-Doolaard (NRG), D. Freis (EC JRC)

SALIENT-01: Preparation and Start of Irradiation of Thorium-Bearing Molten Fluoride Salt in Graphite Crucibles

P. R. Hania, D. A. Boomstra (NRG), O. Benes, P. Soucek (EC JRC), A. J. de Koning, I. Bobeldijk, S. de Groot (NRG), R. J. M. Konings (EC JRC), E. Capelli (Delft Univ of Technol), M. Naji (EC JRC), C. Sciolla, P. J. Baas, V. R. Bhimanadham, N. B. Siccama, G. I. A. Lippens (NRG)

Automating Spent Fuel Defect Detection with Fused DCVD and GET Data

Evangelina Brayfindley (NCSU), Robert Brigantic (PNNL), Ralph C. Smith, John Mattingly (NCSU), Robert Brigantic (PNNL)

Near Real Time Enrichment Verification with Gas Phase UF6 Alpha Spectroscopy

Cari Launiere, Anil Mane (ANL), Kristin Knight, Katherine Charbonnet (Univ of Memphis), Joseph Savina, Jeffrey Elam, Candido Pereira (ANL), William Alexander (Univ of Memphis)

Thermal Conductivity Measurement of Non-Stoichiometric UO2 Pellet for Advanced Nuclear Material Accountancy

Gyeonghun Kim, Jungsu Ahn, Sangjoon Ahn (UNIST)

Process Simulation Tools for Process Control and Safeguards Purpose

B. Dinh, V. Vanel, C. Sorel, A. Duterme, M. Montuir, G. Ferlay (CEA)

IAEA Design Information Verification Authorities for Small Modular Reactors: Potential Challenges and Solutions

D. A. Donnellly, R. T. Otto, C. E. Mathews, B. A. Wilson (PNNL), M. J. Schanfein (INL)

A Neutronic Study of Small Long-Cycle Fast Reactor Core with Recycling

Yeong Uk Jo, Ser Gi Hong (Kyung Hee Univ)

Void Effects in Reactor Charged with Plutonium

B. Gastaldi, R. Eschbach (CEA)

A Collision Probability and Depletion Model for Rapid Scoping and Optimization of Nuclear Reactors

Jessica J. Berry, Andrew G. Osborne (CSM)

Assessment of Annular Metallic Fuel in High-Burnup Fast Reactor

N. E. Stauff, Y. Miao, A. Oaks, T. K. Kim (ANL), S. Hayes (INL)

Uranium Utilization and Material Damage in B&B Reactors with Slightly Enriched Fuel

Chris Keckler, Massimiliano Fratoni, Ehud Greenspan (Univ of California, Berkeley)

FAST (Floating Absorber for Safety at Transient) as a Solution for Positive Coolant Temperature Coefficient in Sodium-Cooled Fast Reactors

Chihyung Kim, Yonghee Kim (KAIST)

Recent Improvements to the Advanced Fuel Cycle Cost Basis Report

Francesco Ganda (ANL), Jason K. Hansen (INL), Kent A. Williams (Consultant), Ed Hoffman (ANL), B. Dixon (INL), T. K. Kim, T. Taiwo (ANL)

Solvent Extraction Flowsheet-Level Modeling and Simulation with Radiolysis

Valmor F. de Almeida, Taha Azzaoui (Univ of Massachusetts Lowell), Kevin L. Lyon (INL)

Scenario Analysis Tool Nuclear Fuel Cycle Simulation System (NFCSS): Safety Assessments in the Context of Spent Fuel Management and Disposal

E. Minari (Tokyo Inst of Technology), K. S. Sim (IAEA), R. Yoshioka (International Thorium Molten-Salt Forum), K. Takeshita (Radioactive Waste Management Funding and Research Center)

Demonstration of Demand Driven Deployment Capabilities in Cyclus

Gwendolyn J. Chee (Univ of Illinois), Jin Whan Bae (ORNL), Robert R. Flanagan (Univ of South Carolina), Roberto E. Fairhurst Agosta, Kathryn D. Huff (Univ of Illinois)

Methods for Automated Fuel Cycle Facility Deployment

Robert R. Flanagan (Univ of South Carolina), Gwendolyn J. Chee (Univ of Illinois), Jin Whan Bae (ORNL), Roberto E. Fairhurst, Kathryn D. Huff (Univ of Illinois)

Estimation of Hydrogen Gas Production at Transient Criticality in Uranyl Nitrate Solution

Ryoichiro Yoshida, Yuichi Yamane, Hitoshi Abe (JAEA)

A Study on the Use of Multiple Liquid Cadmium Cathodes in Electrorefining Process

Gha-Young Kim, Junhyuk Jang, Chang Hwa Lee, Seungwoo Paek, Seung-Jai Lee (KAERI)

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama (JAEA), Hiroyuki Fukuyama, Hideo Higashi (Tohoku Univ.), Tsuyoshi Nishi, Hiromichi Ohta (Ibaraki Univ.), Xiaoxing Liu, Koji Morita (Kyushu Univ.), Kinya Nakamura, Hirokazu Ohta, Masahiro Furuya (CRIEPI)

A Proposed Molten Uranium Thermal Breeder Reactor and Fuel Cycle

Neal L. Mann (Neal Mann & Associates), Mihai (Mike) G. Pop (AREVA NP, Inc.)

Neutronic Analysis of a Liquid Metal Fast Reactor Experiment in the Large-I Position of the Advanced Test Reactor

B. Lilley, T. Palmer (Oregon State Univ), D. LaBrier (Idaho State Univ), A. Higgins, W. Marcum (Oregon State Univ)

Remote Fuel Fabrication Mock-Up

Kiho Kim, Sanggyu Park, Hoon Song, Jeongyong Park (KAERI)

Enhancing MA Transmutation by Irradiation of (MA, Zr)Hx in FBR Blanket Region—Fabrication of (Am, Zr) Alloy

Mutsumi Hirai, Toru Higuchi, Atsushi Ouchi (Nippon Nuclear Fuel Development Co. Ltd.), Kenji Konashi (Tohoku Univ), Hiroaki Muta, Ken Kurosaki (Osaka Univ), Vadim A. Yefimov, Andrey A. Lizin, Sergey V. Tomilin, Alexander G. Osipenko, Sergey S. Poglyad (Joint Stock Company ‘’State Scientific Centre - Research Inst of Atomic Reactors’’)

Experimental Study on Alkali and Alkaline Earth Metal Oxide Solubility in LiCl at 923 K

Dokyu Kang, Seokjoo Yoon (KAIST), Byung Heung Park (Korea National Univ of Transportation), Sungyeol Choi (KAIST)

Zr Separation from High Level Liquid Waste with a Novel Hydroxyacetoamide Type Extractant

K. Morita, H. Suzuki, T. Matsumura (JAEA), Y. Takahashi, T. Omori, M. Kaneko, K. Asano (Toshiba ESS)

Separation Process of Long-Lived Fission Products from High-Level Radioactive Wastes

Yuya Takahashi, Takashi Omori, Eiichi Murata, Yu Yamashita, Masaaki Kaneko, Kazuhito Asano (Toshiba ESS), Keisuke Morita, Hideya Suzuki, Tatsuro Matsumura (JAEA)

Studies on Separation of Platinum Group Metals from High-Level Liquid Waste Using Sulfur-Containing Amide Compounds Fixed Adsorbents

Tatsuya Ito, Naoki Osawa, Haruka Oosugi, Seong-Yun Kim (Tohoku Univ)

Adsorption and Separation of Sr(II) and Y(III) by Extraction Chromatography Using DtBuCH18C6-Impregnated Adsorbent

Seong-Yun Kim, Taiga Kawamura, Tatsuya Ito (Tohoku Univ)

Method for Identifying Waste Types and Data Properties in Radioactive Waste Drums

Hee Seoung Park, Jeoung-Guk Kim, Dae-Seok Hong (KAERI)

Status of Research and Development of Fabricating Large-Size High-Level Waste Pellet by Hot Press

Yoichi Endo, Akihiro Suzuki (Nippon Nuclear Fuel Development)

Lab-Scale Electrorefining Experiments for Decontamination of Intermediate Level Reactor Internals from PWR Decommissioning

Jungho Hur, Sungjune Sohn, Jaeyeong Park (UNIST), Il Soon Hwang (Seoul Natl Univ)

Modeling of Residual Actinide Recovery Process from High-Level Salt Waste Using Molten Salt-Liquid Metal Extraction Process

Byung Gi Park, Hwajeong Han (Soonchunhyang Univ), Bongsoo Lee (Chung-Ang Univ)

Remote Sensing of Radiological Materials in a Wide Area Using Unmanned Aerial Systems

Monia Kazemeini, Alexander Barzilov, Woosoon Yim (UNLV)

Impacts of Fast-Spectrum Molten Salt Reactor Characteristics on Fuel Cycle Performance

Benjamin R. Betzler (ORNL), Andrei Rykhlevskii (Univ of Illinois), Andrew Worrall (ORNL), Kathryn D. Huff (Univ of Illinois)

Initial Accident-Tolerant Fuel/Cladding Extensions to the VERA-to-Bison Offline Coupling

Aaron J. Reynolds (Oregon State Univ), Shane G. Stimpson (ORNL), Russell Gardner (INL)

Effect of Residual Pore on the Thermal-Mechanical Performance of Un Kernel TRISO Particle Fuel

Schichao Liu, Ping Chen , Yi Zhou, Hua Pang, Xong Xi, Changbing Tang, Yanli Zhao, Xi Qiu, Zixuan Guo (Nuclear Power Inst of China)

Research on Thermal Diffusion Coefficient Calculation for Subchannels with Spacer Grid Using CFD Methodology

Xi Chen, Sijia Du, Yu Liu, Libo Qian, Lili Liu (Nuclear Power Inst of China)

Mitigation of Axial Power Peaking in Alternative Heavy Water Reactors Fuels Using Thoriated End Pellets

H. V. Yan, S. Golesorkhi, B. P. Bromley, C. Dugal (CNL)

Reduction Reactions of Vanadium as a Neptunium Analogue with Nitrogen Oxide Species

Michael Chimes, Colin Boxall, Scott Edwards (Lancaster Univ), Mark Sarsfield, Robin J. Taylor, Dave Woodhead (NNL)

Towards the Decontamination of Plutonium Contaminated Bricks: Creation of a Cerium-Based Simulant Contamination System

James Kennedy (Lancaster Univ/NNL), Colin Boxall (Lancaster Univ), Anthony Banford (NNL), Rick Demmer (INL), Andrew Parker (Univ of Central Lancashire)

Incorporation of Platinum-Group Metals in High-Level Waste Borosilicate Glass: Focus on the Capabilities of the Induction Heated Metallic Melter Operated at La Hague Plant

Régis Didierlaurent, Cèline Roussel (Orano), Virginie Labe, Muriel Neyret (CEA), Christophe Renaut, Catherine Veyer (Orano)

Development of High Waste Loading Glasses

Yoshiyuki Miura, Hiroto Mitsuhashi, Taku Hashimoto, Tatsuya Horimai, Takahiro Ishio, Norio Kanehira (JNFL)

Porous Glass Approach for Reduction of Secondary Molybdate Phase in Vitrification of PUREX Raffinate

Kazuyoshi Uruga, Tsuyoshi Usami, Takeshi Tsukada (CRIEPI)

Development of Acid Leaching Method to Retrieve High-Level Wastes from Nuclear Waste Glass

Koichiro Takao, Takahiro Mori, Mayuu Kubo, Yasuhisa Ikeda (Tokyo Inst Technol)

Alteration and Leaching Behavior of Simulated Nuclear Waste Glass in Different Acidic Solutions

Mayuu Kubo, Koichiro Takao (Tokyo Inst Technol)

Long Core Life Design Options for the Westinghouse LFR

T. K. Kim, N. Stauff (ANL), C. Stansbury, A. Levinsky, Fausto Franceschini (Westinghouse)

GEMINI+ Design Options for HTGR Fitting the Requirements for Cogeneration Use in Europe

J. Lavarenne (Wood), V. Amezcua (Empresarios Agrupados), O. Braudrand (IRSN), G. Brinkmann (BriVaTech), W. Brudek (Energoprojekt), M. Davies (Wood), D. Hittner (LGI), J. C. Kuijper (NUCLIC), B. Lindley, J. Lillington (Wood), F. Shahrokhi (Empresarios Agrupados), M. M. Stempniewicz (NRG), D. Vanvor (BriVaTech), G. Wrochna (NCBJ)

The Westinghouse Lead Fast Reactor Program

P. Ferroni, C. Stansbury, J. Liao, D. Utley, A. Levinsky, R. Wright, E. Gustavsson, H. Perry, J. Gorgemans (Westinghouse), S. J. Lee (Fauske & Assosc), M. Ickes, G. Banyay, F. Franceschini, A. Harkness, J. Wills, J. Chrzanowski, B. Friedman, E. Tatli (Westinghouse), G. Grasso, M. Tarantino (Italian National Agency for New Technologies), M. Frignani (Ansaldo Nucleare S.P.A.)

A Molten Fuel Thermal Breeder—A New Solution for Recycling

Neal L. Mann (Neal Mann & Associates), Mihai (Mike) G. Pop (AREVA NP, Inc.)

Interrelationship and the Effects of Introducing Separation Technologies in the Nuclear Fuel Cycle for Enhanced Radioactive Waste Management

Tomohiro Okamura, Eriko Minari, Masahiko Nakase (Tokyo Inst of Technol), Hidekazu Asano (Tokyo Inst of Technol/Radioactive Waste Management Funding and Research Center), Kenji Takeshita (Tokyo Inst of Technol)

Characteristics of TRU Fueled SFR Core During the Partial Loading of LEU Assemblies

Hikaru Hiruta, Brent W. Dixon (INL)

Pyroprocessing Technology Development for Flexible Introduction of Fast Reactor Fuel Cycle

Masatoshi Iizuka (CRIEPI), Toshiyuki Nohira (Kyoto Univ), Kohei Tada (JAEA), Tsuyoshi Murakami (CRIEPI), Hirohide Kofuji (JAEA)

High-Efficiency Dehalogenation of LiCl-KCl Based Electrorefiner Salt Using Protonated Ultrastable Y-Type (USHY) Zeolite via Ion-Exchange

M. S. Wasnik, T. Livingston, K. Carlson, M. F. Simpson (Univ of Utah)

Electrochemical Behavior of Liquid Gallium Electrode in Pyroprocessing

Tsuyoshi Murakami, Masatoshi Iizuka (CRIEPI)

Recent Progress on Development of Pyroprocessing Technology for Minor Actinide Transmutation Nitride Fuels

Hirokazu Hayashi, Takumi Sato, Haruka Tateno, Shin Akashi, Hiroki Shibata, Yasuhiro Tsubata (JAEA)

Volatilization and Trapping of Ruthenium Under a Loss of Cooling Accident on High Level Liquid Waste (HLLW) Storage Tank in Reprocessing Plants

P. Nerisson, M. Barrachin, L. Cantrel, M. Philippe (IRSN)

Conversion of Irradiated Uranium Metal to UO2 for Safe Interim Storage and Final Disposal

Anders Puranen, Kyle D. Johnson, Alexandre Barreiro (Studsvik Nuclear AB), Peter Bennett (Inst for Energiteknikk)

Study on Airborne Release Fraction in Hydrogen Explosion by Comparison Between Overpressurization and Hydrogen Explosion

Yoshikazu Tamauchi, Takahiro Ishio, Takashi Kodama (JNFL), Takashi Kobayashi, Takahiro Chikazawa (Mitsubishi Materials Corp.)

Real-Time Solution Analysis in Microfluidic Devices Using Optical Spectroscopy

Samuel A. Bryan, Amanda M. Lines (PNNL), Gilbert L. Nelson (College of Idaho), Amanda J. Casella, Susan E. Asmussen, Hannah B. Bryan (PNNL), Job M. Bello (Spectra Solutions, Inc)

Tritium Detection by Electrochemical Assisted Radiometrics (TRIBECA)

Ghebrehiwot Berhane, Colin Boxall (Lancaster Univ), Frank Cave (Hybrid Instrument), Malcolm Joyce (Lancaster Univ/Hybrid Instrument), Jackie Pates (Lancaster Univ)

NMR Spectroscopic Studies of Water Dynamics Confined in Cation-Exchanged Montmorillonites

Rongwei Sun, Takehiko Tsukahara (Tokyo Inst Technol)

Life Extension and Accelerated Testing

Michael J. Fluss (NMTC), Edward I. Mosses (Longview Consulting, Inc.)

Benchmark Study on Fuel Performance Codes for Fast Reactors

N. Chauvin (CEA), L. Capriotti (INL), S. Gianfelici (KIT), J. Harp (INL), J. H. Kim (KAERI), M. Lainet (CEA), C. B. Lee (KAIST), T. Ogato, H. Ohto (CRIEPI), T. Ozawa (JAEA), A. Schubert, P. Von Uffelen (JRC), S. Cornet (NEA)

Overview of Axially Heterogeneous PAVIX 8 Fuel in Irradiation in PHENIX Within the Frame of the French GEN IV Development Program

I. Munoz-Viallard, Ph Bienvenu, K. Hanifi, M. Pelletier, M. Masson (CEA)

New Measurements on (U,Pu)O2 Properties Within European Projects: ESNII+ and ESFR-SMART

N. Chauvin (CEA), D. Staicu, D. Nanara, P. Raison (JRC), Ph. M. Martin (CEA)

Development of Barrier Cladding Technology for the Usage of Metal Fuel

Jun Hwan Kim, Sunghwan Yeo, Sung Ho Eom, Sung Ho Kim, Jeong Yong Park (KAERI), Min Soo Lee, Tai Hong Yim (Korea Inst of Industrial Technol)

Postirradiation Examinations of Annular Fast Reactor MOX

F. Cappia, J. Harp (INL), K. Tanaka, M. Kato (JAEA), K. McClellan (LANL)

Technological Development of the Particle Size Adjustment of Dry Recovered Powder

Tomoomi Segawa, Kazuya Yamamoto, Takayoshi Makino, Hidetoshi Iso, Koichi Kawaguchi, Katsunori Ishii, Hisato Sato (JAEA), Tomonori Fukasawa, Kunihiro Fukui (Hiroshima Univ)

Development of Advanced Fabrication Process for Metallic Fuel

Jeong-Yong Park, Kiho Kim, Hoon Song, Seok-Jin Oh, Sang-Gyu Park, Seoung-Woo Kuk, Kyung-Chai Jeong, Ki-Hwan Kim (KAERI)

Prospective Nuclear Fuel Cycle Characteristics of Advanced Nuclear Energy Systems

T. K. Kim, T. A. Taiwo (ANL), B. W. Dixon (INL), M. Todosow (BNL), A. Worrall (ORNL)

Westinghouse Approach to Flexible Power Operation in PWRs

Jeffery A. Brown, Robert E. Becse (Westinghouse)

IAEA On-Going Activities on Power Reactors Fuel Engineering and Spent Fuel Management

Amparo González-Espartero, Mikhail Veshchunov, Ki Seob Sim, Laura McManniman, Christoph Gastl, Clément Hill (IAEA)

Using a Technology and Systems Readiness Assessment to Roadmap a Nuclear Energy R&D Program

B. W. Dixon (INL), W. G. Halsey (LLNL – retired), T. K. Kim (ANL), G. Matthern, N. R. Soelberg (INL), M. Todosow (BNL)

Characterization of HONTA/SiO2-P Adsorbent for MA(III)/Ln(III) Separation Flow-Sheet

Masayuki Takeuchi, Sou Watanabe, Yuichi Sano, Hirohide Kofuji, Hideya Suzuki, Tatsuro Matsumura (JAEA)

Back Extraction Method for Minor Actinide Solvent Extraction Using Solubility-Enhanced Nitrogen-Donor Ligand

Daisuke Watanabe (Hitachi-GE Nuclear Energy/Hitachi), Yuko Kani, Akira Sasahira (Hitachi), Kuniyoshi Hoshino (Hitachi-GE Nuclear Energy)

Electrophoretic Separations of Lanthanum and Gadolinium for Used Nuclear Fuel Reprocessing

Sydney Hodampf, Mark R. Deinert (CSM)

Studies on Lanthanide (III) Hydration Structure in Poly(N-Isopropyl Acrylamide) Polymer Networks Grafted onto Porous

Yokajaksusri Nutthon, Takehiko Tsukahara (Tokyo Inst Technol)

Solvent Washing Schemes for the ALSEP Process Solvent

Dean R. Peterman (INL)

Transport of Irradiated Research Reactor Fuels in the BEA Research Reactor Package

Phillip W. Noss, Richard J. Smith, (Orano)

Use of Multi-Attribute Utility Analyses to Assess Transportation Routes from ISFSIs

Sven Bader, Isabel Srivoraphan, Michael Murray (Orano)

Deep Isolation: Innovative Technology for the Disposal of Spent Nuclear Fuel and Other High-Level Waste

Rodney (Rod) A. Baltzer (Deep Isolation)

Disposition Pathway for Used Nuclear Fuel

Chuck Soderquist, Bruce McNamara, Gregg J. Lumetta, Dallas Reilly (PNNL)

Security and Proliferation Risks Associated with Management of Spent Fuel Nuclear Fuel

Alex Bednarek, Andrew Newman (Nuclear Threat Initiative)

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (2) Effect of B4C Addition on Thermophysical Properties of Austenitic Stainless Steel in a Solid State

Toshihide Takai, Tomohiro Furukawa, Hidemasa Yamano (JAEA)

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (3) Effect of B4C Addition on Thermophysical Properties of Austenitic Stainless Steel in a Liquid State

Hiroyuki Fukuyama, Hideo Higashi (Tohoku Univ), Hidemasa Yamano (JAEA)

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (4) Effect of B4C Addition on Viscosity of Austenitic Stainless Steel in a Liquid State

Hiromichi Ohta, Hiroki Kokubo, Tsuyoshi Nishi (Ibaraki Univ), Hidemasa Yamano (JAEA)

Development of a Fuel Safety Research Program for Metallic Fast Reactor Fuels

C. Jensen, D. Wachs, F. Di Lemma, M. Benson (INL), B. Heath (DOE)

A2-D Correlation to Evaluate Fuel-Cladding Gap Thermal Conductance in Mixed Oxide Fuel Elements for Sodium-Cooled Fast Reactors

J. Lavarenne (Wood), E. Bubelis (KIT), U. Davies (Univ of Cambridge), S. Gianfelici (KIT), S. Gicquel (EdF), J. Krepel (PSI), M. Lainet (CEA), B. Lindley (Wood), K. Mikityuk (PSI), C. Murphy (Wood), B. Perrin (Framatome), W. Pfrang (KIT), A. Ponomarev (PSI), A. Schubert (JRC), E. Shwageraus (Univ of Cambridge), P. Van Uffelen (JRC)

Functionality Isolation Test for Fuel Cycle Code ORION—MOX Fabrication and Depletion

Jin Whan Bae, Eva Davidson (ORNL), Robert Gregg (UK National Lab Springfields Works), Andrew Worrall (ORNL)

Study on the Coordination of Amidoxime Small Molecule Ligands with Uranyl Ions Under Seawater Conditions

Tingting Liu (Harbin Eng Univ/China Inst of Atomic Energy), Suliang Yang, Qian Liu (China Inst of Atomic Energy), Fuqiu Ma, Yun Xue (Harbin Eng Univ), Guoxin Tian (Harbin Eng Univ/China Inst of Atomic Energy)

Energy Market Simulation Tools to Assess Competitiveness of Nuclear Power Plants

N. Stauff, G. Maronati (ANL), P. Talbot (INL), A. Cuadra (BNL), R. Ponciroli, T. K. Kim (ANL), B. Dixon (INL), T. A. Taiwo (ANL)

Examining Plutonium Multirecycling Options for the French Reactor Fleet in Terms of Radioactive Waste Inventories

A. Saturnin, J.-F. Milot, C. Chabert (CEA), F. Laugier (EdF), G. Senentz (Orano), B. Carlier (Framatome)

Multicomponent Mass Transfer of Actinides in Nuclear-Relevant Molten Salts

Haomin Yuan, Nathaniel Hoyt (ANL)

Development of Molten Salt Reactor Modeling and Simulation Capabilities in VERA

Aaron Graham, Benjamin Collins, Robert Salko (ORNL), Zack Taylor (Univ of Tennessee), Cole Gentry (ORNL)

Molten Salt Reactor Transient Analysis Capability of PROTEUS-NODAL

M. K. Jaradat, W. S. Yang (Univ of Michigan), Y. S. Jung, C. H. Lee (ANL)

Safety Analysis of the Molten Salt Fast Reactor Fuel Composition Using Moltres

Sun Myung Park, Andrei Rykhlevskii, Kathryn D. Huff (Univ of Illinois)

Safeguards and Process Modeling for Molten Salt Reactors

Nathan Shoman, Benjamin B. Cipiti (SNL), Benjamin Betzler (ORNL)

Molten Salt Reactor Fuel Depletion Tools in SCALE

Benjamin R. Betzler, Kursat B. Bekar (ORNL), William A. Wieselquist, Shane W. Hart, Shane G. Stimpson (ORNL)

ZIRCEX Pilot Plant Commissioning Lessons Learned

Amy K. Welty, Rick L. Demmer, Richard D. Tillotson, Julia Tripp, Melissa M. Warner (INL)

Optimization of New Extractant Molecules for U(VI)/Pu(IV) Separation

Gaëlle Milanole, Cécile Marie, Manuel Miguirditchian, Christian Sorel (CEA)

Redox Reactions of Fe(III) and AHA in Nitric Acid Solutions in the Context of an Advanced PUREX Process

Suzanne Jones, Colin Boxall (Lancaster Univ), Robin Taylor (NNL)

Progress in Real-time Monitoring for Controlling of the Composition of the Uranium-Plutonium Nitrate Product in a Tri-Butyl Phosphate Based Flowsheet

Gregg J. Lumetta, Jarrod R. Allred, Susan E. Asmussen, Samuel A. Bryan, Gabriel B. Hall, Forrest D. Heller, Amanda M. Lines, Sergey I. Sinkov (PNNL)

Rapid and Efficient Extraction of Inert Platinum Group Metals from HNO3(aq) at Elevated Temperature

Zhiwei Zheng, Tsuyoshi Arai (Shibaura Inst of Technol), Koichiro Takao (Tokyo Inst of Technol)

Spent Fuel Interim Storage with the NUHOMS® HSM Matrix

Prakash Narayanan, William Bracey, Ahmad Salih, (TN Americas LLC)

Evaluation of Aluminum-Clad Spent Nuclear Fuel During Drying and Dry Storage

Rebecca Smith, Daniel Murray, Alexander Winston, Cynthia Adkins, Philip Winston (INL)

Used Fuel Drying by Vacuum and Forced Gas Circulation for Dry Cask Storage

Jonathan E. Perry, Tanvir Farouk, Jamil Khan (Univ of South Carolina), James S. Tulenko (Univ of Florida), Arthur Niemoller (Orano), Travis W. Knight (Univ of South Carolina)

Successful Integration: Bringing Together the High Burnup Spent Fuel Demonstration Project Team

J. A. McEntire, D. McGee (Orano)

Guided Wave Technology

Arthur R. Niemoller (Orano)

A Mechanistic Description of Aerosol Transport and Deposition in Stress Corrosion Cracks

Stylianos Chatzidakis, John Scaglione (ORNL)

System-Wide Impacts of Resolution Options for a Nonconforming Dry Storage System

Stylianos Chatzidakis (ORNL), Efe G. Kurt, Justin L. Coleman (INL), John Scaglione (ORNL), Josh Jarrell (INL)

The Behavior of Analogues for RIS-Affected AGR Cladding Under Conditions Relevant to Wet Interim Storage

Elizabeth Howett (Studsvik Ltd.), Colin Boxall (Lancaster Univ), David Hambley (NNL)

Localized Corrosion Behavior of FeCrAl Nuclear Fuel Cladding in Pool Storage

Raul B. Rebak, R. J. Blair (GE Research), Dan R. Lutz (GE Power)

Temperature-Dependent Crystal Structure of U3SI2 by High-Temperature Neutron Diffraction

Sven C. Vogel (LANL), Tashiema L. Wilson (LANL/Univ of South Carolina), Elizabeth Sooby Wood (LANL/Univ of Texas, San Antonio), Joshua T. White (LANL), Theodore M. Besmann (Univ of South Carolina)

Fabrication and Phase Composition of Alloyed Uranium Silicide Fuels

Elizabeth Sooby Wood, Geronimo Robles, Cole Moczygemba (Univ of Texas at San Antonio), Lu Cai, Peng Xu, Edward Lahoda (Westinghouse)

Nondestructive Examination of Uranium Oxide Kernels Using Energy-Resolved Neutron Imaging

Kristian G. Myhre, Yuxuan Zhang, Hassina Z. Bilheux, Jared A. Johnson, Jean-Christophe Bilheux, Andrew J. Miskowiec, Rodney D. Hunt (ORNL)

Development of FIPD: The EBR-II Fuels Irradiation and Physics Database

Aaron Oaks, Kun Mo, Walid Mohamed, Abdellatif Yacout (ANL)

Analytical Local Stress Model for UMo/Al Dispersion Fuel

Yeon Soo Kim (ANL), G. Y. Jeong (UNIST), K. Mo (ANL)

Proliferation-Protected and Ultra-High Burn-Up Reactor Fuel Produced in Thorium Blanket of a Fusion Neutron Source

G. G. Kulikov, A. N. Shmelev, E. G. Kulikov, V. A. Apse (National Research Nuclear Univ MEPhI)

Effect of Dissolved Mg on the Electrochemistry of Molten MgCl2-NaCl KCl

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

Thermodynamic Estimation of Vaporization of Cesium and Iodine Dissolved in LiF-NaF-KF Molten Salt

Y. Sekiguchi (Univ of Tokyo), T. Kato, K. Uozumi (CRIEPI), K. Kawamura (Tokyo Inst Technol), T. Terai (Univ of Tokyo)

On-Line Monitoring Combined with Spectroelectrochemistry for the Characterization of Uranium and Fission Products Within Molten Salt Environments

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

Stability Study of Platinum and Silver as Quasi-Reference Electrodes for Molten Salt Systems

Dimitris Killinger, Supathorn Phongikaroon (Virginia Commonwealth Univ)

Development of Fuel Debris Treatment Technology by the Fluorination Method

Keita Endo, Kuniyoshi Hoshino, Akira Sasahira, Tetsuo Fukasawa (Hitachi-GE Nuclear Energy, Ltd), Takahiro Chikazawa (Mitsubishi Materials), Akira Kirishima, Nobuaki Sato (Tohoku Univ)

Microfluidic-Based Separation and In-Situ Detection of Selenium(IV) Ion in Radioactive Wastes

Aileen Brandt, Takehiko Tsukahara (Tokyo Inst Technol)

An Approach to the Assessment of the Marginal Value of Neutron Multiplication Factor for the Radioactive Waste Tank

O. N. Andrianova, V. A. Dulin, V. V. Dulin (JSC State Scientific Centre of the Russian Federation), A. A. Andrianov, I. S. Kuptsov, T. A. Frolova (National Research Nuclear University MEPhI)

Compatibility of Pellet Form Storage of High-Level Waste with a Flexible Waste Management System

Akihiro Suzuki, Yoichi Endo (Nippon Nulcear Fuel Developmen), Tetsuo Fukasawa (Hitachi-GE Nuclear Energy), Yusa Muroya (Osaka Univ), Tatsuro Matsumura (JAEA)

Characterization of Ruthenium Tetroxide Capture from Dry Gas Streams by Silica Gel and Metal Surfaces

Barry B. Spencer, Stephanie H. Bruffey (ORNL)