Nuclear Fuel Cycle, Spent Fuel, and Radwaste Management |
Fuel Technology |
ICONE 8-8143 The CAPRA-CADRA Programme / A. Vasile ; G. Vambenepe ; J. C. Lefevre ; K. Hesketh ; W. Maschek ; C. De Raedt ; D. Haas |
ICONE 8-8207 Current Status of Studies on Oxide Pellet Fuel of Fast Reactors in Russia: Irradiation Experience and Post-Irradiation Examination Results / L. M. Zaboudko ; V. M. Poplavsky |
ICONE 8-8221 Mixed Uranium-Refractory Carbide Fuels for Ultra-High Yield Reactors / T. W. Knight ; S. Anghaie |
ICONE 8-8237 Irradiation Performance of a Prototypic Metallic Fuel for Fast Reactors / T. Ogata ; T. Yokoo |
ICONE 8-8266 O/U ratio of UO[subscript 2] Pellets Sintered at Low Temperature and Reduced in Different Atmospheres / B. Ayaz ; A. N. Bilge |
ICONE 8-8378 A Study of the Role of Higher Actinide Burning Fast Reactors in a Hypothetical Future UK Nuclear Fuel Cycle / D. Millington |
ICONE 8-8394 Assembly and Fuel Pin Irradiation Behavior in the BN-350 Fast Reactor / V. N. Karaulov ; A. P. Blynski ; I. L. Yakovlev ; S. V. Golovin ; J. D. B. Lambert |
ICONE 8-8528 Modal Parameters' Evaluation of a Full Scale PWR Fuel Assembly Submitted to Non-Evaluated Excitation / G. Gobillot ; J. Vallory ; R. Nhili |
ICONE 8-8578 Advanced Research Reactor Fuel Development / M. K. Meyer ; G. L. Hoffman ; S. L. Hayes ; J. L. Snelgrove ; T. C. Wiencek ; C. R. Clark ; J. R. Stuart ; R. V. Strain |
ICONE 8-8629 Russian Experience in Using UPuO[subscript 2] Vibropac Fuel Pins in Fast Reactors / A. A. Mayorshin ; O. V. Skiba ; V. A. Tsykanov ; V. A. Kisly |
ICONE 8-8721 Preliminary Analysis on In-Reactor Performance of the Blanket Rod for HYPER / W. Hwang ; B. O. Lee ; W. S. Park |
LWR Fuel Utilization |
ICONE 8-8087 Plutonium Multi-Recycling in PWRs: The CORAIL Concept / S. Aniel ; M. Rohart ; A. Puill ; J. Bergeron ; G. Rouviere |
ICONE 8-8103 High Energy Cores Experience at Westinghouse / A. L. Casadei ; M. Y. Young |
ICONE 8-8232 Regulatory Perspectives on High Burnup Fuel Issues and Burnup Extension / M. S. Chatterton |
ICONE 8-8294 System Modifications in Light Water Reactors for MOX Reloads |
ICONE 8-8391 Nuclear Fuel Non-Destructive Testing Application for Dukovany NPP / M. Lahodova ; J. Vaverka ; M. Valach |
Spent Nuclear Fuel and Nuclear Materials Management |
ICONE 8-8005 In-Vessel Spent Fuel Storage and Simplified Handling System for a Nuclear Heating Reactor / H. Chang ; Y. Wu |
ICONE 8-8164 Empirically-Based Approach for Prediction of Material Storage Temperatures in the Los Alamos Nuclear Materials Storage Facility / J. D. Bernardin ; S. Hopkins ; W. S. Gregory ; S. Zygmunt |
ICONE 8-8180 Cooperative Research Program on Dry Cask Storage Characterization / R. M. Kenneally ; J. H. Kessler |
ICONE 8-8187 Long-Term Storage or Burial of Discharged From Ships Defective, Non-Suited for Reprocessing and Spent Fuel and High-Activity Waste / S. D. Gavrilov ; N. N. Birillo ; S. A. Golovinsky ; V. A. Kremnev ; V V. Ruksha ; P. L. Smirnov ; A. A. Smolyakov |
ICONE 8-8231 Investigation of PFBR Spent Fuel Clad Temperature During Handling / R. Gajapathy ; P. Selvaraj ; P. Chellapandi ; B. S. Sodhi ; S. C. Chetal ; S. B. Bhoje |
ICONE 8-8342 Integrated Testing of a Drying Station for Spent Nuclear Fuel for the BN-350 Fast Reactor / C. E. Baily ; K. E. Rosenberg ; K. J. Allen ; E. A. Howden |
ICONE 8-8348 Decrease of the LWR Spent Nuclear Waste Inventories and Cumulative Fissile Fuel Enrichment in Hybrid Reactor System / O. Ipek |
ICONE 8-8396 The Management by EDF of Radioactive Waste Such as Spent Fuel Storage Rack, Steam Generators and Vessel Heads of PWR NPP / S. Rostain |
ICONE 8-8398 The Design and Fabrication of the Transfer Canister for Spent Nuclear Fuel at the BN-350 Fast Reactor / D. K. Baird ; F. A. Orren |
ICONE 8-8399 The Design and Installation of a Spent Fuel Packaging Cask for the BN-350 Reactor / L. J. Christensen ; M. J. Shannon |
ICONE 8-8498 Design of Plant Hatch Independent Spent Fuel Storage Installation Pads / P. Hsu ; G. V. Jones ; D. P. Moore ; T. S. Springfield ; D. S. Walden |
ICONE 8-8594 High Efficiency One-Stage Melting Converter Method for Vitrification of High-Level Radioactive Wastes / L. S. Pioro ; B. F. Sadovskiy ; I. L. Pioro |
ICONE 8-8597 Design of a Cask Storage Building Based on Numerical Analysis of Natural Convection / H. Ijichi ; H. Kuwabara ; H. Takeda ; M. Mitsuda |
ICONE 8-8627 Hybrid Recycle System for the Recovery of Dirty Plutonium and Pure Uranium / T. Fukasawa ; T. Sawa ; J. Yamashita ; M. Kamoshida ; A. Sasahira ; F. Kawamura |
ICONE 8-8685 Spent Aluminum Plated Fuel Storage System at the Idaho National Engineering and Environmental Laboratory: Technologies and Experience / D. H. Miyasaki ; S. H. Rickard ; J. F. Hanek |
Spent Nuclear Fuel and Waste Processing |
ICONE 8-8099 Studsvik Processing Facility Pyrolysis/Steam Reforming Technology for Volume and Weight Reduction and Stabilization of LLRW and Mixed Wastes / J. B. Mason ; T. W. Oliver ; M. P. Carson ; G. M. Hill |
ICONE 8-8115 Experience in Treatment and Conditioning of Gas Cooled Reactor Metallic Degraded Spent Fuels: The STAR Project / F. Boussard ; S. Fonquernie ; D. Dall'ava |
ICONE 8-8195 Anodic Behaviors of Uranium and Zirconium During Electrorefining Spent Fuel in Molten Salt / S. X. Li |
ICONE 8-8355 Structural Improvement on the Continuous Rotary Dissolver / T. Washiya ; T. Koizumi ; A. Aoshima |
ICONE 8-8373 Development of New Treatment Method to Reduce the Volume of Low Level Liquid Wastes / Y. Saito ; N. Imamoto ; K. Miyata ; M. Karino |
ICONE 8-8374 Development of New Treatment Method to Reduce the Volume of Chlorinated Organic Solid Wastes |
ICONE 8-8388 Development of Integrated Treatment System for Liquid/Solid Wastes / H. Sagawa ; H. Fukui ; Y. Kuwayama ; T. Ueno ; K. Tanimoto ; H. Katayama ; N. Uda |
ICONE 8-8449 Development of an Information Management and Communication System for the Second Progress Report for HLW Disposal in Japan / M. Shiotsuki ; H. Ishikawa ; S. Masuda ; S. Fusaeda ; I. Yanagisawa ; A. Neyama |
ICONE 8-8540 Flowfield Characteristics in a Model Vaneless Diffuser Prior to Stall Inception / K. B. Abidogun ; S. A. Ahmed |
ICONE 8-8541 Engineering and Acquisition of Equipment for Electrometallurgical Treatment of Spent Nuclear Fuel / J. E. Herceg ; K. J. Belcher ; L. Bova ; H. J. Haupt ; S. A. Kamal ; J. G. Saiveau |
ICONE 8-8659 Anatomy of Waste Operations at Argonne National Laboratory - East / C. W. Grandy ; C. M. Rock |
ICONE 8-8671 Technology Development for Nuclear Fuel Cycle: Radioactive Waste Treatment and Spent Fuel Storage / M. Kikuchi ; T. Yoshida ; M. Matsuda ; T. Izumida |
ICONE 8-8702 Design and Development of a Cathode Processor for Electrometallurgical Treatment of Spent Nuclear Fuel / A. R. Brunsvold ; P. D. Roach ; B. R. Westphal |
ICONE 8-8714 Mortar Matrices for Radioactive Waste Materials Physico-Chemical Characterization in Preaging Tests Due to Addition of the Polyethylene Granules and Powder / A. D. Peri |
Codes, Standards, and Regulatory Issues |
Design Codes and Standards Issues |
ICONE 8-8227 Basis and Formulation of Toughness Requirements for Section III, Div. 3 of the ASME Code / S. Yukawa |
ICONE 8-8238 Codes and Standards Redesign Using Advanced Web-Based Solutions / R. S. Hill III ; R. W. Barnes |
ICONE 8-8411 Impact of Environmental Factors on Nuclear Components: A New Section III Appendix / W. Z. Novak |
ICONE 8-8413 Recent Developments in the ASME Boiler and Pressure Vessel Code Section III / C. J. Pieper ; R. M. Jessee ; E. B. Branch |
Risk-Informed ISI |
ICONE 8-8165 A Risk-Informed Approach to IGSCC Weld Examinations / M. R. Graybeal |
ICONE 8-8211 Industry and Regulatory Initiatives on Risk-Informed Inservice Inspection of Nuclear Piping / S. A. Ali ; S. Dinsmore |
ICONE 8-8296 Developments on Implementation of U.S. NRC-Approved WOG Risk-Informed Inservice Inspection Methodology / K. R. Balkey ; N. B. Closky ; B. A. Bishop ; M. H. Canton ; R. L. Haessler ; G. L. Sharp ; P. R. Stevenson |
ICONE 8-8298 Risk-Informed Inservice Inspection: Full Implementation Via Integration of Augmented Programs / P. O'Regan |
ICONE 8-8383 Quantitative Assessment of a Risk Informed Inspection Strategy for BWR Weld Overlays / K. N. Fleming ; J. Mitman |
ICONE 8-8622 Implementation Results of Risk-Informed Inservice Inspection Application at Arkansas Nuclear One, Unit Two / L. Shay ; M. J. Paterak ; K. C. Panther ; R. A. Fougerousse ; R. S. Smith |
Risk-Informed IST |
ICONE 8-8212 Cost/Benefit Evaluation of Implementing Pump and Valve RI-IST at a Nuclear Power Plant / C. W. Rowley |
ICONE 8-8278 BandWOG Risk-Informed Inservice Testing Demonstration Project for Air-Operated Valves / G. K. Estep ; R. S. Enzinna |
ICONE 8-8293 Implementation of an Air Operated Valve Program at Northern States Power Company / J. R. Schaefer ; R. B. Worrell ; P. Szetu |
ICONE 8-8340 ASCO NPP Risk-Informed Inservice Testing Program for Check Valves / I. Mach ; R. Losa ; L. Mendez ; J. Faig |
ICONE 8-8748 Operation and Maintenance Guideline on IST of Dynamic Restraints (Snubbers) for Nuclear Power Stations in Japan / H. Iwami ; M. Yokoe ; C. Kojima |
Development of PRA Standard |
ICONE 8-8255 Probabilistic Risk Assessment: Why a Standard Is Needed / M. T. Drouin ; M. A. Cunningham ; T. L. King ; G. M. Holahan ; R. J. Barrett ; A. M. Ramey-Smith |
ICONE 8-8710 The American Nuclear Society PRA-Standards Project / R. J. Budnitz |
MOV and AOV Issues |
ICONE 8-8047 Verifying Design Basis Capability of Motor-Operated Valves / S. Loehein |
ICONE 8-8228 NRC Regulatory and Research Activities on Performance and Safety-Related Motor-Operated Valves at U.S. Nuclear Power Plants / J. E. Jackson ; T. G. Scarbrough |
ICONE 8-8326 Motor-Operated Valve (MOV) Activities in Korea and Canada / M. R. Holbrook ; W. T. Kim ; A. L. Grant |
ICONE 8-8380 Summary of a Study of Air-Operated Valves in U. S. Nuclear Power Plants, NUREG/CR-6654 (INEEL/EXT-98-00383) / O. O. Rothberg |
ICONE 8-8515 Motor-Operated Valve Performance Monitoring / P. W. Searfoorce ; G. F. Sessler |
ICONE 8-8604 Joint Owner's Group Air Operated Valve Program / M. D. Coleman |
Air and Gas Treatment Issues |
ICONE 8-8153 High Efficiency Metal Filters for Nuclear Air and Gas Treatment: HEMA Filters and Their New AG-1 Code Section / L. D. Weber |
ICONE 8-8630 Evaluation of HEPA Filter Service Life (RFP-5141) / J. K. Fretthold ; A. R. Stithem |
ICONE 8-8631 ASME AG-1 Code on Nuclear Air and Gas Treatment / R. D. Porco |
Cranes With Enhanced Safety for Increased Profit |
ICONE 8-8077 X-SAM: The Single-Failure-Proof Crane System / J. E. Nelson |
ICONE 8-8544 ASME Nuclear Crane Standards for Enhanced Crane Safety and Increased Profit / S. N. Parkhurst |
ICONE 8-8545 Flux Vector Controls for Increased Reliability, Performance, and Safety / A. J. Orgovan |
ICONE 8-8546 Nuclear Containment Telescoping Boom Jib Crane / D. P. Weber |
ICONE 8-8547 Cranes at NASA's Kennedy Space Center Utilizing Enhanced Mechanical and Electrical Safety Features / B. P. Lytle |
Nuclear Quality Assurance Issues |
ICONE 8-8215 Nuclear Quality Assurance Standards and Regulations: Evolution and Issues / M. E. Langston ; S. A. Bernsen |
ICONE 8-8248 Software Quality Assurance and the NQA-1 Standard / R. C. Schrotke |
ICONE 8-8694 Graded Application of NQA Standards to Research and Development Activities / F. C. Hood |
Other Regulatory Issues |
ICONE 8-8365 Maintaining Nuclear Safety Competence of Regulatory Staff Into the 2000's / A. M. Omar ; I. Grant ; N. Belisle |
C and S Strategic Planning Issues |
ICONE 8-8782 Strategic Planning for Codes and Standards in Japan / M. Higuchi |
ICONE 8-8783 Strategic Planning for ASME Nuclear Codes and Standards / J. H. Ferguson |
ICONE 8-8636 Recent Changes in French Regulation and Codes for Nuclear and Non-Nuclear Pressure Components / C. Faidy |
ASME Research Issues |
ICONE 8-8299 The Development of Risk-Informed Qualification (RIQ) Guidelines for Active Mechanical Equipment / B. M. Ayyub ; R. K. Perdue |
ICONE 8-8321 Improved Methods for Estimating the Distribution and Density of Defects in Welds Used in Reactor Piping / O. J. V. Chapman ; F. A. Simonen ; R. S. DeCesare |
ICONE 8-8354 Risk-Informed Technology Developments Within the American Society of Mechanical Engineers for Nuclear Power Plants |
ASME Code Case N-589 Cured-In-Place-Pipe |
ICONE 8-8243 Use of Reinforced Epoxy as a Structural Lining System / R. H. Walker |
ICONE 8-8389 Why Was the N-589 Code Case Developed......and Revised? / J. T. Conner ; C. W. Wesley |
ICONE 8-8681 Cured-in-Place Piping Application for Structural and Pressure Boundary Integrity / J. A. Charest |
Author Index |
Nuclear Fuel Cycle, Spent Fuel, and Radwaste Management |
Fuel Technology |
ICONE 8-8143 The CAPRA-CADRA Programme / A. Vasile ; G. Vambenepe ; J. C. Lefevre ; K. Hesketh ; W. Maschek ; C. De Raedt ; D. Haas |
ICONE 8-8207 Current Status of Studies on Oxide Pellet Fuel of Fast Reactors in Russia: Irradiation Experience and Post-Irradiation Examination Results / L. M. Zaboudko ; V. M. Poplavsky |
ICONE 8-8221 Mixed Uranium-Refractory Carbide Fuels for Ultra-High Yield Reactors / T. W. Knight ; S. Anghaie |
ICONE 8-8237 Irradiation Performance of a Prototypic Metallic Fuel for Fast Reactors / T. Ogata ; T. Yokoo |