Performance of Near-Weapons-Grade Plutonium Fuel Pins in Commercial Light Water Reactors (English)
- New search for: Difilippo, F. C.
- New search for: Fisher, S. E.
- New search for: Difilippo, F. C.
- New search for: Fisher, S. E.
In:
NUCLEAR TECHNOLOGY
;
133
;
310-324
;
2001
-
ISSN:
- Article (Journal) / Print
-
Title:Performance of Near-Weapons-Grade Plutonium Fuel Pins in Commercial Light Water Reactors
-
Contributors:Difilippo, F. C. ( author ) / Fisher, S. E. ( author )
-
Published in:NUCLEAR TECHNOLOGY ; 133 ; 310-324
-
Publisher:
- New search for: AMERICAN NUCLEAR SOCIETY
-
Publication date:2001-01-01
-
Size:15 pages
-
ISSN:
-
Type of media:Article (Journal)
-
Type of material:Print
-
Language:English
- New search for: 621.48
- Further information on Dewey Decimal Classification
-
Classification:
DDC: 621.48 -
Source:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Table of contents – Volume 133
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 1
-
TECHNICAL PAPERS - FISSION REACTORS - ATBR -- A Thorium Breeder Reactor Concept for Early Induction of Thorium in an Enriched Uranium ReactorJagannathan, V. et al. | 2001
- 1
-
ATBR-A Thorium Breeder Reactor Concept for Early Induction of Thorium in an Enriched Uranium ReactorJagannathan, V. / Pal, U. / Karthikeyan, R. / Ganesan, S. / Jain, R. P. / Kamat, S. U. et al. | 2001
- 33
-
TECHNICAL PAPERS - REACTOR SAFETY - Kinetics of Gaseous Iodine Uptake onto Stainless Steel During Iodine-Assisted CorrosionWren, Jungsook Clara et al. | 2001
- 33
-
Kinetics of Gaseous Iodine Uptake onto Stainless Steel During Iodine-Assisted CorrosionWren, J. C. / Glowa, G. A. et al. | 2001
- 50
-
TECHNICAL PAPERS - FUEL CYCLE AND MANAGEMENT - Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding Under Reactivity-Initiated-Accident ConditionsFuketa, Toyoshi et al. | 2001
- 50
-
Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding Under Reactivity-Initiated-Accident ConditionsFuketa, T. / Sasajima, H. / Sugiyama, T. et al. | 2001
- 63
-
Experimental Investigation of Mixing Phenomena Inside a Concrete Containment Cooled by an Innovative Passive SystemBrusa, L. / Bianchi, A. / Fruttuoso, G. / Manfredini, A. / Oriolo, F. / Carelli, M. D. / Kendig, R. P. / Peters, F. E. et al. | 2001
- 63
-
TECHNICAL PAPERS - THERMAL HYDRAULICS - Experimental Investigation of Mixing Phenomena Inside a Concrete Containment Cooled by an Innovative Passive SystemBrusa, Luigi et al. | 2001
- 77
-
Investigation of Core Thermohydraulics in Fast Reactors-Interwrapper Flow During Natural CirculationKamide, H. / Hayashi, K. / Isozaki, T. / Nishimura, M. et al. | 2001
- 77
-
TECHNICAL PAPERS - THERMAL HYDRAULICS - Investigation of Core Thermohydraulics in Fast Reactors -- Interwrapper Flow During Natural CirculationKamide, H. et al. | 2001
- 92
-
Evaluation of Impurity Behavior in the Reactor Water of a Boiling Water ReactorIgarashi, H. / Ohta, N. / Usui, N. / Ohsumi, K. / Uchida, S. / Matsui, T. et al. | 2001
- 92
-
TECHNICAL PAPERS - NUCLEAR PLANT OPERATIONS AND CONTROL - Evaluation of Impurity Behavior in the Reactor Water of a Boiling Water ReactorIgarashi, Hiroo et al. | 2001
- 103
-
TECHNICAL PAPERS - REPROCESSING - Removal of Zirconium in Electrometallurgical Treatment of Experimental Breeder Reactor II Spent FuelAhluwalia, Rajesh K. et al. | 2001
- 103
-
Removal of Zirconium in Electrometallurgical Treatment of Experimental Breeder Reactor II Spent FuelAhluwalia, R. K. / Hua, T. Q. / Geyer, H. K. et al. | 2001
- 119
-
Neutron Radiography Flow Visualization of Liquid Metal Injected into an Empty Vessel and a Vessel Containing Saturated WaterSibarmoto, Y. / Nakamura, H. / Anoda, Y. et al. | 2001
- 119
-
TECHNICAL PAPERS - RADIOISOTOPES - Neutron Radiography Flow Visualization of Liquid Metal Injected into an Empty Vessel and a Vessel Containing Saturated WaterSibamoto, Yasuteru et al. | 2001
- 133
-
Assessment of TRAC-BF1 for Waterhammer Calculations with Entrapped AirBrinckman, K. W. / Chaiko, M. A. et al. | 2001
- 133
-
TECHNICAL NOTE - THERMAL HYDRAULICS - Assessment of TRAC-BF1 for Waterhammer Calculations with Entrapped AirBrinckman, Kevin W. et al. | 2001
- 141
-
TECHNICAL PAPERS - FISSION REACTORS - Development of a Simulation Model and Safety Evaluation for a Depressurization Accident Without Reactor Scram in an Advanced HTGRNakagawa, Shigeaki et al. | 2001
- 141
-
Development of a Simulation Model and Safety Evaluation for a Depressurization Accident Without Reactor Scram in an Advanced HTGRNakagawa, S. / Saikusa, A. / Kunitomi, K. et al. | 2001
- 153
-
PLUTON: A Three-Group Model for the Radial Distribution of Plutonium, Burnup, and Power Profiles in Highly Irradiated LWR Fuel RodsLemehov, S. / Nakamura, J. / Suzuki, M. et al. | 2001
- 153
-
TECHNICAL PAPERS - FUEL CYCLE AND MANAGEMENT - PLUTON: A Three-Group Model for the Radial Distribution of Plutonium, Burnup, and Power Profiles in Highly Irradiated LWR Fuel RodsLemehov, Sergei et al. | 2001
- 169
-
TECHNICAL PAPERS - THERMAL HYDRAULICS - Multidimensional TMI-1 Main-Steam-Line-Break Analysis Methodology Using TRAC-PF-NEMIvanov, Kostadin N. et al. | 2001
- 169
-
Multidimensional TMI-1 Main-Steam-Line-Break Analysis Methodology Using TRAC-PF/NEMIvanov, K. N. / Beam, T. M. / Baratta, A. J. / Irani, A. / Trikouros, N. G. et al. | 2001
- 187
-
Assessment of the ATHENA Code for Calculating the Void Fraction of a Lead-Bismuth/Steam Mixture in Vertical UpflowDavis, C. B. et al. | 2001
- 187
-
TECHNICAL PAPERS - THERMAL HYDRAULICS - Assessment of the ATHENA Code for Calculating the Void Fraction of a Lead-Bismuth-Steam Mixture in Vertical UpflowDavis, Cliff B. et al. | 2001
- 194
-
Corium Oxidation at Temperatures Above 2000 KHagrman, D. L. / Rempe, J. L. et al. | 2001
- 194
-
TECHNICAL PAPERS - THERMAL HYDRAULICS - Corium Oxidation at Temperatures Above 2000 KHagrman, Donald L. et al. | 2001
- 213
-
TECHNICAL PAPERS - NUCLEAR PLANT OPERATIONS AND CONTROL - Neural Network with Local Memory for Nuclear Reactor Power Level ControlUluyol, Önder et al. | 2001
- 213
-
Neural Network with Local Memory for Nuclear Reactor Power Level ControlUluyol, O. / Ragheb, M. / Tsoukalas, L. et al. | 2001
- 229
-
TECHNICAL PAPERS - RADIOACTIVE WASTE MANAGEMENT AND DISPOSAL - Transmutation of Elemental Cesium by a Fusion Neutron SourceSaito, Masaki et al. | 2001
- 229
-
Transmutation of Elemental Cesium by a Fusion Neutron SourceSaito, M. / Apse, V. A. / Artisyuk, V. V. / Chmelev, A. N. et al. | 2001
- 242
-
TECHNICAL PAPERS - RADIOACTIVE WASTE MANAGEMENT AND DISPOSAL - Concepts in Waste Management: Cerium-Promoted Dissolution of Refractory Actinide OxidesTedder, Daniel Willlam et al. | 2001
- 242
-
Concepts in Waste Management: Cerium-Promoted Dissolution of Refractory Actinide OxidesTedder, D. W. / Finney, B. C. et al. | 2001
- 253
-
Modeling of Hydrodynamic Chromatography for Colloid Migration in Fractured RockLi, S.-H. / Jen, C.-P. et al. | 2001
- 253
-
TECHNICAL PAPERS - RADIOACTIVE WASTE MANAGEMENT AND DISPOSAL - Modeling of Hydrodynamic Chromatography for Colloid Migration in Fractured RockLi, Shih-Hai et al. | 2001
- 264
-
DEPARTMENT - Letters to the Editor| 2001
- 269
-
TECHNICAL PAPERS - REACTOR SAFETY - Application of the Integrated TH-PA Method to the Westinghouse AP600 DesignGuan, Yue et al. | 2001
- 269
-
Application of the Integrated TH-PA Method to the Westinghouse AP600 DesignGuan, Y. / Li, F. / Modarres, M. / Bessette, D. / Dimarzo, M. et al. | 2001
- 290
-
TECHNICAL PAPERS - REACTOR SAFETY - A Method of Integrating Thermal-Hydraulic Analysis and Probabilistic Assessment for Safety Evaluation and ScreeningGuan, Yue et al. | 2001
- 290
-
A Method of Integrating Thermal-Hydraulic Analysis and Probabilistic Assessment for Safety Evaluation and ScreeningGuan, Y. / Li, F. / Modarres, M. et al. | 2001
- 310
-
Performance of Near-Weapons-Grade Plutonium Fuel Pins in Commercial Light Water ReactorsDifilippo, F. C. / Fisher, S. E. et al. | 2001
- 310
-
TECHNICAL PAPERS - FUEL CYCLE AND MANAGEMENT - Performance of Near-Weapons-Grade Plutonium Fuel Pins in Commercial Light Water ReactorsDifilippo, Felix C. et al. | 2001
- 325
-
TECHNICAL PAPERS - FUEL CYCLE AND MANAGEMENT - A Modification of the Inner and Outer Core for Reactor Pressure Vessel Lifetime ExtensionSeo, Bo Kyun et al. | 2001
- 325
-
A Modification of the Inner and Outer Core for Reactor Pressure Vessel Lifetime ExtensionSeo, B. K. / Kim, J. K. / Shin, C. H. / Kwon, T. J. et al. | 2001
- 338
-
TECHNICAL PAPERS - REPROCESSING - Prediction of a Breakthrough Curve of Iodine on a Reduced Silver-Loaded Adsorbent BedTakeshita, Kenji et al. | 2001
- 338
-
Prediction of a Breakthrough Curve of Iodine on a Reduced Silver-Loaded Adsorbent BedTakeshita, K. / Nakano, Y. et al. | 2001
- 346
-
TECHNICAL NOTES - FISSION REACTORS - Generation, Testing, and Validation of a WIMS-D-4 Multigroup Cross-Section Library Based on the JENDL-3.2 Nuclear DataRahman, Mafizur et al. | 2001
- 346
-
Generation, Testing, and Validation of a WIMS-D/4 Multigroup Cross-Section Library Based on the JENDL-3.2 Nuclear DataRahman, M. / Takano, H. et al. | 2001
- 355
-
Development Program of LOCA Licensing Calculation Capability with RELAP5-3D in Accordance with Appendix K of 10 CFR 50.46Liang, T. K. S. / Schultz, R. R. et al. | 2001
- 355
-
TECHNICAL NOTES - THERMAL HYDRAULICS - Development Program of LOCA Licensing Calculation Capability with RELAP5-3D in Accordance with Appendix K of 10 CFR 50.46Liang, Thomas K.S. et al. | 2001
- 359
-
DEPARTMENTS - Volume 133 Indexes| 2001
-
DEPARTMENTS - Volume 133 Contents| 2001