Past Programming (incomplete listing) 2004 Annual Meeting / Pittsburgh, PA Fuels and Materials Performance Reactor Pressure Boundary Penetration Degradation—Panel ICAPP Embedded Topical Materials/Corrosion Issues of Supercritical Water Reactors (Panel) Structural and Materials Modeling and Analysis Materials for Space Reactor Concepts Fuel Design and Irradiation Issues for Next Generation Plants Advanced Issues in Welding and Materials 2003 Winter Meeting / New Orleans, LA Nuclear Materials Testing Nuclear Fuel Testing and Analysis US DOE Nuclear Engineering Education Research: Highlights of Recent and Current Research I & II (Co-sponsor) 2003 Annual Meeting / San Diego, CA Advances in Nuclear Fuel Material Corrosion in Liquid Metal and CO2 Coolants 2002 Winter Meeting / Washington, DC Nuclear Fuel Materials Materials for Fusion Energy and Hydrogen Storage Materials Research for Lead Alloy Reactors Materials Aging Research Sponsored by the Nuclear Energy Plant Optimization (NEPO) Program Student Research in Nuclear Materials Science and Technology–Poster Session Fuels for Transmutation (Co-sponsor) 2002 Annual Meeting / Hollywood, FL Advances in Nuclear Fuels Advances in Nuclear Materials Advanced Fuel Cycle Options for Reactors (Co-sponsor) 2001 ANS Winter Meeting / Reno, NV Advances in Nuclear Fuels and Materials Materials Compatibility in Liquid-Metal Coolants—I Materials Compatibility in Liquid-Metal Coolants—II Student Mini-Conference - Materials Technology Section 2001 ANS Annual Meeting / Milwaukee, WI Corrosion In Nuclear Systems Fuels For Space Nuclear Power Systems 2000 ANS Winter Meeting / Washington, DC Advanced Fuels and Materials Student Research in Nuclear Materials Science and Technology 1999 ANS Winter Meeting / Long Beach, CA Advanced Fuels 1999 ANS Annual Meeting / Boston, MA Accelerator-Driven Systems and Spallation Neutron Sources Nuclear Methods in Materials Research 1998 ANS Winter Meeting / Washington, DC MSTD General Session Transient Fuel Behavior 1997 ANS Winter Meeting / Albuquerque, NM MSTD General Session Survey of Materials for Nuclear Technology Applications
	2004 Annual Meeting / Pittsburgh, PA Fuels and Materials Performance Chair: Rober Hanrahan (LANL) Mechanistic Understanding of Primary Water Stress Corrosion Cracking of Alloy 600 in PWR Water, Ji Hyun Kim, Il Soon Hwang (Seoul National Univ) Development of Intraspecimen Method for the Application to Life Prediction, Hoi Su Choi, Ji Hyun Kim, Il Soon Hwang (Seoul National Univ) Assessment of the DUPIC Fuel Performance for the In-Core Fuel Management Strategy, Hangbok Choi, Ho Jin Ryu (KAERI) Investigation of Trace Hydrogen Uptake in Lithium-Ion Battery Using Prompt Gamma Activation Analysis, S. K. Aghara, S. Venkatraman, A. Manthiram (Univ of Texas-Austin)
	2004 Annual Meeting / Pittsburgh, PA Reactor Pressure Boundary Penetration Degradation—Panel Session Organizers: Todd Allen (Univ. of Wisconsin), Jean-Marie LeCorre (Westinghouse). Chair: Todd Allen
	2003 Winter Meeting / New Orleans, LA Nuclear Fuel Testing and Analysis Chair: Donald D. Lanning (PNNL) Advances in Thermophysical Properties Measurements of Nuclear Fuels at Very High Temperatures, Mikhail Sheindlin (ITE) Validation of the PLATE Code for Predicting U-Mo/Al Fuel Plate Swelling, S. L. Hayes (ANL), R. A. Brazener (Penn State) Transmuter Fuel Fabrication: Design and Analysis of Robotic Manufacturing Processes, Georg F. Mauer, Jamil Renno (Univ of Nevada, Las Vegas) Wet Storage for RBMK-Type Reactor Spent Fuel: A Life Prolongation Problem, E. D. Fedorovich (St. Petersburg State Tech Univ), U. K. Petrenya (Central Boiler-Turbine Inst), L. V. Scmakov (Leningrad NPP), E. A. Repnikova (Texas A&M)
	2003 Winter Meeting / New Orleans, LA Nuclear Materials Testing Chair: Ronald Ballinger (MIT) Thermal Creep of V-4Cr-4Ti in a Lithium Environment, S. E. O'Rourke, M. L. Grossbeck (Univ of Tennessee) Mitigation of Primary Water Stress Corrosion Cracking by Nickel-Plating Methodology, Ji Hyun Kim, Si-hyoung Oh, Il Soon Hwang (Seoul Natl Univ) A Modified Crack Formation Technique for Nuclear Steam Generator Tubing, Tae Hyun Lee, Young Jin Oh, Il Soon Hwang (Seoul Natl Univ), Han Sub Chung (KEPRI), Jang Yul Park (ANL) Pb-Bi and Materials Compatibility Test Using HELIOS Facility, S. H. Jeong, N. Y. Lee, I. S. Hwang (Seoul Natl Univ)
	2003 Annual Meeting / San Diego, CA Advances in Nuclear Fuel Session Organizers: David Senor (PNNL), Ronald G. Ballinger (MIT) The Effect of Design and Uncertainty on Coated Particle Fuel Reliability, J. Wang, R. G. Ballinger (MIT) Modeling Fission Gas Release in CERCER Fuel, Y. Long, Y. Yuan, M. S. Kazimi (MIT) QA/QC for Advanced Fuel Particle Production, R. L. Hockey, L. J. Bond, M. S. Good (PNNL), J. N. Gray (Iowa State Univ) The Effect of Rare Earth Dopants on UO2 Oxidation, B. D. Hanson, S. E. Cumblidge, R. D. Scheele, R. L. Sell (PNNL) Some Electrical Properties of UO2—Part 1, T. T. Meek (Univ of Tennessee), B. G. Von Roedern (Natl Renewable Energy Lab), M. J. Haire (ORNL)
	2003 Annual Meeting / San Diego, CA Material Corrosion in Liquid Metal and CO2 Coolants Session Organizer: Todd Allen (ANL-West) Research Update on Liquid Metal Corrosion at the Idaho National Engineering and Environmental Laboratory, E. Loewen (INEEL) In-Situ Corrosion Observation of Iron Base Material Under Sodium Peroxide, T. Furukawa, K. Aoto (Japan Nucl Cycle Dev Inst) Corrosion Testing for a Supercritical CO2 Cooled Fast Reactor, E. Loewen, K. Weaver (INEEL) Corrosion of Steels After Exposure to PbBi at 420–600°C, G. Mueller, A. Heinzel, G. Schumacher, A. Weisenburger (FzK) Experimental Studies on the Corrosion of Fe-Si, Fe-Cr, and Fe-Cr-Si Alloys in Pb-Bi Eutectic, J. Lim, R. G. Ballinger, P. W. Stahle (MIT)
	2002 Winter Meeting / Washington, DC Nuclear Fuel Materials Session Organizer: Travis Knight (Univ of Florida) Electronic Properties of Defect Complex in Uranium Dioxide, Hunhwa Lim, Younsuk Yun, Kwangheon Park (Kyung Hee Univ–Korea), Kun Woo Song (KAERI, Taejon–Korea) Silver Migration and Release in Thin Silicon Carbide, H. J. MacLean, R. G. Ballinger (MIT) Post-Operation Characterization of EBR-II Primary System Components, B. R. Seidel, R. W. King, D. Baird, M. Huntley, M. Sayer, F. Orren (ANL-Idaho) Advanced Burnable Poisons in Pressurized Water Reactors, K. Allen, R. Blaney, D. Butt, J. Kim, J. Tulenko (Univ of Florida) Comparison of the Swelling Fits Developed for Russian and American Austenitic Steels Before Reaching Steady-State Conditions, Fatma Yilmaz (Texas A&M)
	2002 Winter Meeting / Washington, DC Materials for Fusion Energy and Hydrogen Storage Session Organizers: James Stubbins (Univ of Illinois), Robert Hanrahan (LANL) Helium Trapping Capacity in Advanced Ferritic Steels, Yuya Matsushita (Kyoto Univ–Japan) Gas Nuclear Transmutation Effects in Aluminum Nitride, Tatsuo T. Shikama (Tohoku Univ–Japan) Search for Radioluminescent Materials Working at Elevated Temperature, K. Toh (Tohoku Univ–Japan), T. Kakuta (JAERI–Japan), T. Shikama (Tohoku Univ–Japan) Hydrogen Storage in Diamond Films, Mark A. Prelas, Tushar K. Ghosh, Robert V. Tompson, Jr., Sudarshan K. Loyalka (Univ of Missouri, Columbia)
	2002 Winter Meeting / Washington, DC Materials Aging Research Sponsored by the Nuclear Energy Plant Optimization (NEPO) Program Session Organizer: Todd Allen (ANL-Idaho) The Nuclear Energy Plant Optimization Program, G. Morris (DOE), G. J. Toman (EPRI), T. R. Allen (ANL-Idaho) NEPO 3-30 Project: In Situ NDT Measurements of Irradiation-Induced Swelling in PWR Core Internal Components, I. I. Balachov (SRI Int), F. A Garner (PNNL), Y. Isobe (NFI-Japan), H. Tang (EPRI) Plastic Flow and Fracture of Cold-Worked 316 Stainless Steel, R. Daum, T. Allen, J. Cole (ANL-Idaho), H. Tsai (ANL), D. Porter (ANL-Idaho), B. Wirth (LLNL), P. Spatig (EPF–Switzerland) Demonstration of High-Burnup Fuel in Dry Cask Storage, Mikal A. McKinnon (PNNL), Glenn W. Morris (DOE, Germantown), Albert Machiels (EPRI)
	2002 Winter Meeting / Washington, DC Materials Research for Lead Alloy Reactors Session Organizer: Travis Knight (Univ of Florida) Experimental Study of the Corrosion of Fe-Si Alloys in Liquid Pb, J. Lim, R. G. Ballinger, P. W. Stahle (MIT) Tensile Testing of 410 Stainless Steel Exposed to Pb-Bi Eutectic, Eric P. Loewen (INEEL), Keyna I. Riley (Purdue Univ) HT-9 Corrosion Growth in Flowing Pb-Bi at 550 and 650°C, Eric P. Loewen (INEEL), Hannah Yount (Univ of Missouri, Rolla) Ultrasonic Examination Versus Scanning Electron Microscopy for Analyzing Lead Corrosion in Stainless Steel, Eric P. Loewen (INEEL)
	2002 Annual Meeting / Hollywood, FL Advances In Nuclear Fuels Session Organizer: David Senor (PNNL) 1. RIA Investigation for High Burnup ThO2-UO2 Fuel, Y. Long, R. G. Ballinger, J. E. Meyer, M. S. Kazimi (MIT) 2. Cermet Fuel for the Thorium Fuel Cycle, S. M. McDeavitt (ANL), T. J. Downar, A. A. Solomon (Purdue Univ) 3. The Thermal Diffusivity of Uranium Dioxide and MOX Up to 100.000 MWd/t , C. Ronchi, D. Halton, M. Sheindlin, D. Staicu (European Commission JRC–Germany), M. Kinoshita, (CRIEPI Japan) 4. Design for Irradiation Tests in the HFR with Innovative Fuel, T. Ozawa, T. Abe, S. Kono (JNC–Japan), K. Bakker, H. Thesingh (NRG–The Netherlands), Ch. Hellwig, F. Ingold, H. Wallin (Scherrer Inst–Switzerland) 5. New Fuel Pellet Design for the Enhancement of Safety Parameters in a CANDU Fuel Bundle, Yong-Deog Kim, Dong-Hwan Park, Ho-Cheol Shin, Chang-Sub Lee (KEPRI–Korea) 6. The CANFLEX-NU Lead Test Assemblies Demonstration Irradiation at Wolsong-1 Nuclear Power Plant, Yong-Deog Kim, Seok-Jean Lyou, Ho-Cheol Shin, Yong-Bae Kim, Chang-Sub Lee (KEPRI–Korea) 7. The Safety Evaluation of the CANFLEX-NU Fuel for Loading into Wolsong-1 Nuclear Power Plant, Yong-Deog Kim, Hwang-Yong Jun, Yong-Bae Kim, Chang-Sub Lee (KEPRI–Korea) 8. Revised UO2 Thermal Conductivity for Frapcon-3 NRC Fuel Performance Codes, D. D. Lanning, C. E. Beyer (PNNL)
	2002 Annual Meeting / Hollywood, FL Advances In Nuclear Materials Session Organizer: David J. Senor (PNNL) 1. SiC/SiC Composites for Advanced Nuclear Applications, R. H. Jones, D. J. Senor (PNNL) 2. Ceramic-Metal Interfaces in Nuclear Materials Applications, S. M. McDeavitt (ANL) 3. Understanding Flow Induced Vibration and Fretting Wear in PWR Fuel, S. J. King, Roger Y. Lu (Westinghouse, Columbia), D. V. Paramonov (Westinghouse STD) 4. Monitoring and Evaluation of SG Crevice Chemistry Evolution, Chi Bum Bahn, Sihyoung Oh, Byoung Gi Park, Il Soon Hwang (Seoul Natl Univ–Korea), In Hyoung Rhee (Soonchunhyang Univ–Korea), Uh Chul Kim, Jung Won Na (KAERI, Taejon–Korea) 5. In Situ Raman Spectroscopic Investigation of Alloy 600 in Simulated PWR Water, Ji Hyun Kim, Il Soon Hwang (Seoul Natl Univ–Korea)
	2002 Annual Meeting / Hollywood, FL Advanced Fuel Cycle Options For Reactors (Co-Sponsor) Session Organizer: K. Michael Goff (ANL-Idaho) 1. Influence of Moderation Ratio on Several Equilibrium Fuel Cycles of PWR, Hiroshi Sekimoto, Abdul Waris (Tokyo Inst Technol–Japan) 2. Optimization of Thorium-Based Seed and Blanket Fuel Assembly Design for PWR, Kwan-Hee Kim, Kang-Mok Bae, Myung-Hyun Kim (Kyung Hee Univ–Korea) 3. Validation Comparison of SCALE-4.3 Using the 27 and 44 Group Cross-Section Libraries for Uranium Systems with Enrichments Between 0.72 and 10.0 wt% 235U, Richard Montgomery (Nucl Fuel Svc), Rose Montgomery (Montgomery Tech Svc), Shane Parkey (Univ of Tennessee) 4. A Study on the Optimal Loading Pattern Based upon Multi-Objective Optimization, Yong Se Kwon, Un Chul Lee (Seoul Natl Univ–Korea), Kyung Ho Cho, Yoon Jun Lee (Cheju Natl Univ–Korea) 5. Optimum Cycle Length and Discharge Burnup for Nuclear Fuel, J. Secker, B. Johansen, H. Lam, M. Hone (Westinghouse), R. McCord, R. Tropasso, J. Morrow, E. Young, T. Rieck (Exelon), O. Ozer, K. Edsinger (EPRI), S. Yilmaz, K. Ivanov, B. Sarikaya (Penn State)
	2001 Winter Meeting / Reno, Nevada Advances In Nuclear Fuels And Materials Sponsored by the Materials Science and Technology Division Cosponsored by the Fuel Cycle and Waste Management and the Operations and Power Divisions Session Organizers: James S. Tulenko (Univ of Florida), Carl Beard (Univ of Texas, Austin) 1. Development of N-Type Diamond Semiconductor Through Field Enhanced Diffusion by Optical Activation, Dickerson C. Moreno, M. Prelas, T. K. Ghosh (Univ of Missouri, Columbia) 2. A Fission Gas Release Model for High Burnup ThO2-UO2 Fuel, Y. Long, Y. Yuan, M. S. Kazimi, R. G. Ballinger (MIT) 3. Effects of Rim Microstructure on High Burnup UO2 Fuel Performance, Chan Bock Lee, Dae Ho Kim, Je Geon Bang, Young Min Kim, Yong Sik Yang, Youn Ho Jung (KAERI–Korea)
	2001 Winter Meeting / Reno, Nevada Materials Compatibility In Liquid-Metal Coolants—I Sponsored by the Materials Science and Technology Division Cosponsored by the Accelerator Applications Division Session Organizer: Todd Allen (ANL-Idaho) 1. Present Status of Study on Compatibility of Steels in LBE, Kazumi Aoto, Tomohiro Furukawa (JNC–Japan) 2. A Test System for Experimental Studies of Liquid-Metal-Structural-Material Interaction, J. Lim, P. W. Stahle, R. G. Ballinger (MIT) 3. Heavy Metal Coolant Corrosion Testing Using a Gas Lift Apparatus, Eric P. Loewen, Philip E. MacDonald (INEEL) 4. Corrosion of Zirconium, 316 and 410 Stainless Steel, F-22, and HT-9 Exposed to High Temperature Heavy Metal Coolant Under Extreme Conditions, Eric P. Loewen, Philip E. MacDonald (INEEL)
	2001 Winter Meeting / Reno, Nevada Materials Compatibility In Liquid-Metal Coolants—II Session Organizer: Todd Allen (ANL–Idaho) 1. Corrosion of Stainless Steels by Lead-Based Reactor Coolants, L. Leibowitz, V. A. Maroni, S. M. McDeavitt, A. G. Raraz, A. J. Kropf (ANL) 2. Study of Lead-Bismuth Technology at JAERI, Toshinobu Sasa, Shigeru Saito, Kenji Kikuchi, Yuji Kurata, Masatoshi Futakawa (JAERI CNS–Japan) 3. Corrosion of Steels in a Flowing Nonisothermal Pb-Bi, Minoru Takahashi, Tadashi Suzuki, Hiroshi Sekimoto (Tokyo Inst Technol–Japan) 4. Compatibility Evaluation of Fuel Cladding Materials for LMFBR in Sodium, Eiichi Yoshida, Yasushi Hirakawa (JNC–Japan) 5. Effects of Oxygen Potential on Corrosion of Steel in Sodium, K. Aoto, E. Yoshida, Y. Tadokoro (JNC–Japan) 6. The Effect of Tungsten on Microstructural Changes During Creep of 10Cr-Mo Steel, Sung Ho Kim, B. J. Song, Woo Seog Ryu (KAERI, Taejon–Korea)
	2001 Winter Meeting / Reno, Nevada Student Mini-Conference Materials Technology Section Study on Improvement of Critical Heat Flux by g-Ray Irradiation, Hiroshi Akiyama, Koji Okamoto, Haruki Madarme ~Univ of Tokyo–Japan!, Tomoji Takamasa ~Tokyo Univ of Merc Marine–Japan The Effect of Electric Field And Laser Beams in the Diffusion of Boron into Polycrystalline Diamond Films, Alejandro Suarez, Mark A. Prelas, Tushar K. Ghosh, Sudarshan Loyalka, Robert V. Tompson, Dabir S. Viswanath ~Univ of Missouri, Columbia Doping of Diamond Films with Phosphorus Through Field Enhanced Diffusion by Optical Activation, Dickerson C. Moreno, M. Prelas, T. K. Ghosh ~Univ of Missouri, Columbia Delayed Hydride Cracking of Cladding Materials Heidi Aquino ~UNLV Diffusion of Boron in Single-Crystal Diamond (Type IIa) Using Field Enhanced Diffusion, Bai-Ling Hsu, Mark A. Prelas, Tushar K. Ghosh, Robert V. Tompson, S. Loyalka, D. Viswanath ~Univ
	2001 ANS Annual Meeting / Milwaukee, WI Fuels For Space Nuclear Power Systems Session Organizer: Samim Anghaie (Univ of Florida) 1. Tri-Carbide Nuclear Fuel Processing and Characterization for Space Nuclear Applications, Travis Warren Knight, Samim Anghaie (Univ of Florida) 2. Compatibility of Tungsten and Molybdenum with UF4 and UF4-UO2 at 2000 to 2350 K, Robert Joseph Hanrahan, Jr. (L ANL), Samim Anghaie (Univ of Florida) 3. Innovative Semispherical Pb-Hf-Cu Shield for a Fissioning Plasma Core Reactor, Travis Warren Knight, Samim Anghaie (Univ of Florida)
	2001 ANS Annual Meeting / Milwaukee, WI Corrosion In Nuclear Systems Session Organizer: Todd Allen (ANL-Idaho) 1. Liquid Lead Corrosion Under Reducing Conditions with Arsenic Present, Eric P. Loewen (INEEL) 2. Analysis of Data for Large-Effect Mercury Targets of LANSCE/WNR Experiments, S. H. Kim, R. P. Taleyarkhan (ORNL) 3. The Role of Cavitation on Initiating Mercury- SteelWetting, Rusi P. Taleyarkhan, Seokho H. Kim, Steven J. Pawel, James R. DiStefano (ORNL) 4. Comparison of the PWR Cladding Corrosion Models for Test IFA-638.1-3, Yong-Deog Kim,Seong-Man Bae, Chang-Sup Lee (KEPRI–Korea)
	2000 ANS Winter Meeting / Washington, DC Advanced Fuels and Materials There is growing interest in advanced nuclear fuels development. This interest is driven by a variety of factors, including the decision of the United States to dispose of the majority of its surplus weapons plutonium inventory through the use of mixed-oxide fuel, as well as a desire to develop more proliferation-resistant fuel forms for use as more countries turn to a closed fuel cycle. The advent of the Nuclear Energy Research Initiative (NERI) signaled a renewed interest in nuclear energy research in the United States. The U.S. Department of Energy designed the NERI program to address key issues affecting the future of the nation's nuclear energy supply and to preserve the existing nuclear science and engineering experience base. Of the 45 seminal NERI projects funded in 1999, approximately 20 involve materials science and technology issues that range from the corrosion of nuclear materials to the fabrication and performance of advanced fuel materials. In addition to NERI, other recent DOE-NE programs, including NEER and NEPO, also support research in materials science and technology. This session considered the full spectrum of materials research sponsored by DOE-NE and other programs and provided a forum for the discussion of materials issues that are critical for the future of nuclear energy in the United States. The intent of this session was to provide a forum for discussion and dissemination of results relevant to nuclear fuel development, both for near-term fuel forms and longer-term development activities. Session Organizers: Carl Beard and Sean McDeavitt A list of the papers presented in this special session is presented below. The extended abstracts for the papers may be found in Transactions of the American Nuclear Society. KL Peddicord and PG Medvedev (Texas A&M University) "Analyzing Thermomechanical Behavior of LEU and Weapons-Grade MOX Fuel Pins in WWER-1000 Using the COMETHE-4D and FRAPCON-3 Fuel Performance Codes." TK Kim, CH Kim and TJ Downar (Purdue University) "Thorium Fuel Depletion Analysis for Boiling Water Reactors." SM McDeavitt (ANL), TJ Downar (Purdue University), MC Hash (ANL), S Revankar, AA Solomon, Y Xu (Purdue University), AS Hebden, D Walker (ANL), W Robey, J Xiu (Purdue University) "Development of a Mixed-Oxide Cermet Dispersion Fuel Using (Th,U)O2 in a Zirconium Metal Matrix TR Allen, JI Cole, NL Dietz (ANL-W), Y Wang, GS Was (University of Michigan), EA Kenik (ORNL) "The Effect of Bulk Composition on Microstructural Changes in Austenitic Alloys." B Hao, B Packer (Gamma Engineering), R Wagner (McDermott Technologies), D Donovan, J Baker (Swales Aerospace), G Kohse (MIT) "Testing Advanced Ceramic Composite Cladding for Water Reactors: A NERI Progress Report."
	2000 ANS Winter Meeting / Washington, DC Student Research in Nuclear Materials Science and Technology Students are the future of nuclear research and development. The earlier students can become involved in professional society activities, the more likely they will continue that involvement throughout their careers. The purpose of this session was to provide current and recent students a professional-level forum to present their research in materials related projects relevant to nuclear technologies. A best-paper contest was held to encourage participation and reward outstanding effort. Session Organizer: Carl Beard A list of the papers presented in this special session is presented below. The extended abstracts for the papers may be found in Transactions of the American Nuclear Society. B Brickner, L Presseley, JS Tulenko (University of Florida) "An Innovative Spectral Shift Burnable Poison Rod Assembly Design." SK Aghara, R Lebouf, CA Beard (University of Texas) "Feasibility Study of a Proliferation-Resistant Fuel Form for Plutonium Recycling." GD Willis (University of Missouri-Rolla), EP Loewen (INEEL) "Corrosion Studies Using Liquid-Lead Alloys." BG Park, CB Bahn, IS Hwang (Seoul National University-Korea) "Modification of Ag/AgCl Electrode Design for Use in LWR Water." JH Kim, YJ Oh, IS Hwang (Seoul National University-Korea) "Fracture Behavior of Heat-Affected Zones in Low-Alloy Steels." K Jeong, YJ Oh, JH Kim, IS Hwang (Seoul National University-Korea) "Dynamic Fracture Testing of Ferritic Steels Using the DCPD Method" J Lim, RG Ballinger (MIT) "Development of a Facility for the Study of Liquid-Metal-Structural Material Interaction." The winners of the best-paper awards were: First Place ($250) - SK Aghara (University of Texas) Second Place ($150) - L Presseley (University of Florida) Third Place ($50) - K Jeong (Seoul National University-Korea) Third Place ($50) - G Willis (University of Missouri-Rolla)
	1999 ANS Annual Meeting / Boston, MA Accelerator-Driven Systems and Spallation Neutron Sources Session Organizer: Jim Stubbins (Univ Illinois) Materials selection and performance issues are central to all applications of nuclear technology. Emerging non-traditional applications of nuclear science pose particular materials challenges. Accelerator systems are currently under development for a variety of applications including tritium production, neutron sources, and waste transmutation. Several programs in the United States and around the world are developing accelerator-driven systems where neutrons produced by spallation are used for isotope production, waste processing, neutron science, materials science, spent fuel conversion, and other applications.  Target, blanket and structural materials in these systems are exposed to severe environments.  Performance considerations include radiation damage from neutron and charged particle irradiation, corrosion from contact with a variety of fluids, and high temperature operation.  The Materials Science and Technology Division held a special session at the 1999 ANS Annual Meeting to address some of the current issues associated with nuclear materials in accelerator-driven and spallation neutron systems. The session explored radiation and other effects on materials in accelerator-driven systems.  Selection criteria and severe life assessments for materials in these systems was considered as well. The papers presented in this session are listed below. Extended abstracts were published in Transactions of the American Nuclear Society. "Materials for Spallation Neutron Sources, with Emphasis on the SNS Facility," LK Mansur (ORNL) "PKA Spectrum and Radiation Damage for 150-MeV Electrons on Type 316 Stainless Steel," Y Zheng, MS Wechsler, MH Barnett, DJ Dudziak (NCSU) and LK Mansur (ORNL) "Latest Calculations of Radiation Damage at SNS," MH Barnett, MS Wechsler, DJ Dudziak (NCSU), LA Charlton and LK Mansur (ORNL) "Radiation Damage Calculations for the APT Materials Test Program," RK Corzine, MS Wechsler, DJ Dudziak (NCSU), PD Ferguson and MR James (LANL) "Moderator Materials for the Spallation Neutron Source," LA Charlton (ORNL)
	1999 ANS Annual Meeting / Boston, MA Nuclear Methods in Materials Research Session Organizer: Kenan Unlu (Cornell) Materials selection and performance issues are central to all applications of nuclear technology. Emerging non-traditional applications of nuclear science pose particular materials challenges. Nuclear methods are widely used in materials research, particularly for materials characterization. Some nuclear techniques are used as a probe to determine the structure while others are used for chemical analysis. Neutron scattering, neutron diffraction, neutron reflectometry and x-ray methods are some of the examples used in materials structure characterization. Neutron depth profiling, neutron activation analysis and prompt gamma activation analysis are examples of the chemical analysis techniques that require measurements of nuclear radiation produced by neutron capture. The Materials Science and Technology Division held two special sessions at the 1999 ANS Annual Meeting to address some of the current issues associated with nuclear methods in materials research. Diverse applications of these nuclear methods in materials research were included in these sessions. The papers presented in this session are listed below. Extended abstracts were published in Transactions of the American Nuclear Society. "Rutherford Backscattering Measurements at Medium Energies Using a Pulsed Beam Time-of-Flight System," RR Hart (Texas A&M), LA Foster (LANL), BD Lansrud, KG Thompson, and PE Tissot (Texas A&M). "Residual Stress Analysis for Engineering Applications by Means of Neutron Diffraction," T Gnaupel-Herold (Univ Maryland/NIST), PC Brand and HJ Prask (NIST). "Small-Angle Neutron-Scattering Measurements of Deuteride Formation in Nb," BJ Heuser, W Chen, and JW Althauser (Univ Illinois) "High-Resolution Neutron Imaging with Microchannel Plates," WB Feller (NOVA Scientific), RG Downing (RGD Research) and PL White (NOVA Scientific). "Hydrogen Measurement in Cladding Material by Neutron Transmission Analysis," BA Hilton (ANL-West) and RT Klann (ANL). "The Application of Neutron Activation Analysis to Materials Research," DA Becker (NIST) "Materials Characterization at the NIST Cold Neutron Depth Profiling Instrument," GP Lamaze and H Chen-Mayer (NIST). "Trace Determination of Boron in Various Materials by a Neutron Induced Prompt-Gamma-Ray Analysis," C Yonezawa and H Matsue (JAERI). "Materials Characterization by Cold Neutron Prompt-Gamma-Ray Activation Analysis," RL Paul (NIST) "Applications of Neutron Depth Profiling in Materials Science," RG Downing (RGD Research) and K Unlu (Cornell). "Nanocavity Generation in Materials Studied by Neutron Depth Profiling and Positron Beam Analysis," A van Veen, F Labohm and H Schut (Delft UT).
	1999 ANS Winter Meeting / Long Beach, CA Advanced Fuels The importance of developments in nuclear fuel remains central to progress in fission reactor technology. In the United States, recent programs such as the Nuclear Engineering Research Initiative (NERI) and disposition of excess weapons material have brought nuclear fuels issues back to the forefront. In other countries, fuels development continues to progress for light water reactors, heavy water reactors, and fast reactors. The implementation of commercial fuel reprocessing programs in several countries has created many opportunities for materials science and technology research. Work on evolutionary and revolutionary nuclear fuels has relevance for improving the safety and performance of existing nuclear power plants and developing the technologies necessary for next-generation fission reactors. The Materials Science and Technology Division of ANS held a special session at the 1999 ANS Winter Meeting to address some of the current issues associated with advanced nuclear fuels. The papers focused on materials science and technology rather than on programmatic or policy issues. Extended abstracts were published in Transaction of the American Nuclear Society. The titles, authors and author affiliations are listed below for the four papers presented in this session. "An Advanced Equation of State of UO2 up to the Critical Point," I. Iosilevski (MIPT-Russia), G. Hyland (Univ Warwick-UK), C. Ronchi (ITE-Germany), and E. Yakub (Odessa Med St Univ-Ukraine). "Transmutation of Actinide Nuclear Wastes Using a Hydride Fuel Target," K. Konashi (Tohoku Univ-Japan), M. Yamawaki (Univ Tokyo-Japan), K. Fujimura and T. Sanda (Hitachi ERL-Japan). "Thermal Conductivity of U-ZrHx and U-Th-Zr-H," B. Tsuchiya, J. Huang, K. Konashi (Tohoku Univ-Japan), M. Teshigawara (JAERI SNL-Japan) and M. Yamawaki (Univ Tokyo-Japan). "Properties of Zirconia-Based Fuels for Plutonium Utilization in Reactors," M.A. Pouchon, C. Degueldre (Paul Scherrer Inst-Switzerland) and P. Tissot (Univ Geneva-Switzerland).
	1998 ANS Winter Meeting / Washington, DC MSTD General Session The Materials Science and Technology Division sponsors a General Session at each ANS Annual and Winter Meeting. The General Session provides a forum for the timely presentation of research that is not encompassed by the thematic programming developed for a particular Meeting. Papers are solicited that address scientific and engineering topics associated with materials for any nuclear application. A list of papers to be presented at the 1998 ANS Annual Meeting is provided below. "Irradiation Performance of FBR Monju-Type Fuel with Modified Type 316 Stainless Steel at High Burnup," S Ukai, T Yoshitake, N Akasaka, T Donomae, K Katsuyama, T Mitsugi and T Asaga (PNC Oarai-Japan). "Evaluation of Helium Gas Release Behavior in MOX Fuel," K Katsuyama, T Mitsugi, T Asaga (PNC Oarai-Japan). "MOX Fuel Performance for the 21st Century," PC Childress, RC Kingsley (B&W Lynchburg), P Nutall (BNFL) and JS Tulenko (University of Florida). "Method for Sputtering Thin Metallic Films on Millimetre-Diameter Polyester Spheres," GH Miley and M Williams (University of Illinois). "Accurately and Quickly Detecting Fuel Pin Leaks without Shutting Down Boiling Water Reactors," M Sattler (RWD Technologies).
	1998 ANS Winter Meeting / Washington, DC Transient Fuel Behavior This session is concerned with both experimental and modeling efforts for fuel rod behavior during reactor transient or accident conditions. The session will cover separate effects and integral experiments. Model development and sophisticated computer code development and validation will also be considered. Fuel transient phenomena of particular interest include fuel material properties, fuel and cladding oxidation behavior, fuel volatilization, foaming and melting, fuel/clad interaction, fuel liquefaction and dissolution, fission product transport in the fuel matrix and fuel-to-clad gap, fission product trapping in the cladding, fission product vaporization, fuel and fission product thermochemistry, and fuel rod behavior during reactivity-initiated accidents. A list of the papers scheduled for presentation in the session is provided below. "Defective Fuel Rods During Severe Accident Conditions - I: Gap Transport," BJ Lewis (Royal Military College-Canada). "Defective Fuel Rods During Severe Accident Conditions - II: Oxidation Processes," BJ Lewis (Royal Military College-Canada). "Using the ELSA and MFPR Release Codes to Interpret the VERCORS 4 and 5 Experiments," R Dubourg (IPSN-France), N Davidovich (ENEA-Italy), MP Kissane (IPSN-France) and G Ducros (CEA Grenoble-France). "Fission Product Release During Transient Heating of Irradiated CANDU Fuel," Z Liu, Z Bilanovic, DS Cox, RS Dickson, LW Dickson (AECL Chalk River-Canada). "Toward a Comprehensive Thermodynamic Treatment of Noble Metal Inclusions," MH Kaye (Queen's University-Canada), WT Thompson and BJ Lewis (Royal Military College-Canada). "A Review of Experiments and Results from the TREAT Facility," LW Deitrich, CE Dickerman, AE Klickman and AE Wright (Argonne National Laboratory). "Experimental Capabilities of the TREAT Facility," DC Crawford (Argonne National Laboratory-West), LW Deitrich, RE Holtz (Argonne National Laboratory), RW Swanson (Argonne National Laboratory-West) and AE Wright (Argonne National Laboratory).
	1997 ANS Winter Meeting / Albuquerque, NM MSTD General Session The Materials Science and Technology Division sponsors a General Session at each ANS Annual and Winter Meeting. The General Session provides a forum for the timely presentation of research that is not encompassed by the thematic programming developed for a particular Meeting. If a sufficient number of papers is not received to fill a session (typically at least three or four), then the accepted papers will be provided to another Division for inclusion in an appropriate alternate forum. A list of the papers presented in this general session is presented below. The extended abstracts for the papers may be found in Transactions of the American Nuclear Society, Volume 77, 1997. The page numbers given below for each paper refer to the appropriate pages in this volume. CS Eberle, "Literature Review of Metal Corrosion Sensitivity in High-Impurity Hot Cell Atmospheres," pp. 163-164. JF Stubbins, KD Leedy and MM Li, "Mechanical Performance of Copper/Stainless Steel Bonded Panels for Fusion Primary-Wall Applications," pp. 160-161. S Sahin, A Sahinaslan, M Kaya and S Yilmaz, "Radiation Damage in Liquid-Protected First-Wall Materials for MFE Reactors," pp. 158-160.
	1997 ANS Winter Meeting / Albuquerque, NM Survey of Materials for Nuclear Technology Applications Materials selection and performance issues are central to all a