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ANS > Publications > Journals > Nuclear Technology > Volume 127 |
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Number 1 · Number 2 · Number 3 |
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Number 1 · July 1999 |
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• Table of Contents |
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Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries
Volume 127 · Number 1 · July 1999 · Pages 1-23
Technical Paper · Fission Reactors  Luiz C. Leal, Otto W. Hermann, Stephen M. Bowman, Cecil V. Parks |
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Drag Coefficients for Reactor Loose Parts
Volume 127 · Number 1 · July 1999 · Pages 24-37
Technical Paper · Thermal Hydraulics Liang Shi, J. Michael Doster, Charles W. Mayo |
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Modeling the Statics of a Natural-Circulation Boiling Water Reactor Loop
Volume 127 · Number 1 · July 1999 · Pages 38-48
Technical Paper · Thermal Hydraulics Haico V. Kok, Tim H. J. J. van der Hagen |
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Qualification of a Three-Dimensional Core Dynamics Analysis Program Coupled with a Detailed Mesh Division for Commercial Boiling Water Reactors-I
Volume 127 · Number 1 · July 1999 · Pages 49-65
Technical Paper · Thermal Hydraulics Yasunori Bessho, Takafumi Anegawa, Osamu Yokomizo, Yuichiro Yoshimoto, Masao Chaki, Motoo Aoyama, Takanori Fukahori |
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Natural Convection Heat Transfer with Crust Formation in the Molten Metal Pool
Volume 127 · Number 1 · July 1999 · Pages 66-80
Technical Paper · Thermal Hydraulics Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, Sang-Min Choi |
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Separation of Radioactive Strontium from Alkaline Nuclear Waste Solutions with the Highly Effective Ion Exchanger SrTreat
Volume 127 · Number 1 · July 1999 · Pages 81-87
Technical Paper · Radioactive Waste Management and Disposal Jukka Lehto, Leena Brodkin, Risto Harjula, Esko Tusa |
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Dose Rate Measurements and Calculation of TN-12/2 Packages
Volume 127 · Number 1 · July 1999 · Pages 88-101
Technical Paper · Radioactive Waste Management and Disposal Hiroaki Taniuchi, Fumio Matsuda |
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Empirical Steam Generator Water-Level Modeling Using Neural Networks
Volume 127 · Number 1 · July 1999 · Pages 102-112
Technical Paper · Materials for Nuclear Systems Chaung Lin, Tsung-Ming Lin |
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Theoretical Calculations of Proton Reaction Cross Sections in a Lead Target with Energy Ep  300 MeV
Volume 127 · Number 1 · July 1999 · Pages 113-122
Technical Paper · Radiation Measurements and Instrumentation Jinfeng Zhou, Qingbiao Shen, Xiuquan Sun |
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Uncertainty Analysis in DUPIC Fuel-Cycle Cost Using a Probabilistic Simulation Method
Volume 127 · Number 1 · July 1999 · Pages 123-140
Technical Note · Fuel Cycle and Management Won Il Ko, Jong Won Choi, Jae Sol Lee, Hyun Soo Park, Kun Jai Lee |
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Number 2 · August 1999 |
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• Table of Contents |
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A MELCOR-Based Model to Calculate Vapor Natural Circulation in Pressurized Water Reactor High-Pressure Severe Accidents
Volume 127 · Number 2 · August 1999 · Pages 141-150
Technical Paper · Reactor Safety Francisco Martín-Fuertes Hernández-Sonseca |
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Modeling of the Rim Effect on Thermal Behavior of High-Burnup UO2 Fuel
Volume 127 · Number 2 · August 1999 · Pages 151-159
Technical Paper · Fuel Cycle and Management Byung-Ho Lee, Yang-Hyun Koo, Dong-Seong Sohn |
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A Condensation Experiment in the Presence of Noncondensables in a Vertical Tube of a Passive Containment Cooling System and Its Assessment with RELAP5/MOD3.2
Volume 127 · Number 2 · August 1999 · Pages 160-169
Technical Paper · Thermal Hydraulics Hyun Sik Park, Hee Cheon No |
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Core Damage Severity Evaluation for Pressurized Water Reactors by Use of Fuzzy Logic Algorithms
Volume 127 · Number 2 · August 1999 · Pages 170-185
Technical Paper · Reactor Operations and Control Anastasios Mironidis, Leon Lidofsky, George Grochowski, Lefteris Tsoukalas |
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Conceivable Limits for Thermal Reactor Spent-Fuel Recycling
Volume 127 · Number 2 · August 1999 · Pages 186-198
Technical Paper · Reprocessing David R. Kingdon, Vladimir A. Khotylev, Archie A. Harms, J. Eduard Hoogenboom |
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Matrix Diffusion of Simple Cations, Anions, and Neutral Species in Fractured Crystalline Rocks
Volume 127 · Number 2 · August 1999 · Pages 199-211
Technical Paper · Radioactive Waste Management and Disposal Haruo Sato |
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Evaluation of the Effect of Temperature on Potassium Clinoptilolite Ion Exchange
Volume 127 · Number 2 · August 1999 · Pages 212-217
Technical Paper · Materials for Nuclear Systems David A. White, Andreas Nattkemper, Radu Ratautiu |
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Design of the European Spallation Source Liquid-Metal Target Using Computational Fluid Dynamics
Volume 127 · Number 2 · August 1999 · Pages 218-232
Technical Paper · Accelerators Trevor V. Dury, Brian L. Smith, Günter S. Bauer |
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An Electrocatalyzed Process for Leaching of Plutonium from Active Gauntlets and Subsequent Separation by Solvent Extraction
Volume 127 · Number 2 · August 1999 · Pages 233-237
Technical Note · Reprocessing K. Venugopal Chetty, P. M. Mapara, A. G. Godbole, Rajendra Swarup |
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Number 3 · September 1999 |
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• Table of Contents |
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Feasibility Studies of a Soluble Boron-Free 900-MW(electric) PWR, Safety Systems: Consequences of the Partial or Total Elimination of Soluble Boron on Plant Safety and Plant Systems Architecture
Volume 127 · Number 3 · September 1999 · Pages 239-258
Technical Paper · Fission Reactors Gian Luigi Fiorini, Guy Marie Gautier, Yves Bergamaschi |
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Feasibility Studies of a Soluble Boron-Free 900-MW(electric) PWR, Core Physics - I: Motivations, Assembly Design, and Core Control
Volume 127 · Number 3 · September 1999 · Pages 259-266
Technical Paper · Fission Reactors Paul Thomet |
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Feasibility Studies of a Soluble Boron-Free 900-MW(electric) PWR, Core Physics - II: Control Rod Follow, Load Follow, and Reactivity-Initiated Accident Linked to RCCAs
Volume 127 · Number 3 · September 1999 · Pages 267-286
Technical Paper · Fission Reactors Jean-Paul Deffain, Philippe Alexandre, Paul Thomet |
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Hybrid Analysis of the Simplified Boiling Water Reactor Using RAMONA-4B and CASMO-3 Computer Codes
Volume 127 · Number 3 · September 1999 · Pages 287-300
Technical Paper · Reactor Safety Gabriel F. Cuevas Vivas, Yassin A. Hassan |
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Benchmark Calculations of the ESADA Single-Region Mixed-Oxide Critical Experiments
Volume 127 · Number 3 · September 1999 · Pages 301-314
Technical Paper · Reactor Safety Hatice Akkurt, Naeem M. Abdurrahman |
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Benchmark Calculations of the Saxton Plutonium Program Critical Experiments
Volume 127 · Number 3 · September 1999 · Pages 315-331
Technical Paper · Reactor Safety Naeem M. Abdurrahman, Georgeta Radulescu, Igor Carron |
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Behavior of a UF6 Container During a Fire - I: Analysis and Phenomenological Interpretation of Tenerife Experimental Results
Volume 127 · Number 3 · September 1999 · Pages 332-351
Technical Paper · Thermal Hydraulics Eric Pinton, Bernard Duret, Georges Berthoud |
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Behavior of a UF6 Container in a Fire - II: Modeling and Validation
Volume 127 · Number 3 · September 1999 · Pages 352-374
Technical Paper · Thermal Hydraulics Eric Pinton, Bernard Duret, Georges Berthoud |
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Uranium Dioxide Powder Preparation, Pressing, and Sintering for Optimum Yield
Volume 127 · Number 3 · September 1999 · Pages 375-381
Technical Paper · Materials for Nuclear Systems Palanki Balakrishna, Chandru K. Asnani, R. M. Kartha, K. Ramachandran, K. Sarat Babu, Vaidyanathan Ravichandran, Bhallamudi Narasimha Murty, Chaitanyamoy Ganguly |
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Pressurized Water Reactor Coolant Pump Locked Rotor Analysis Methodology Using RETRAN-02 and FREY
Volume 127 · Number 3 · September 1999 · Pages 382-388
Technical Note · Thermal Hydraulics Lainsu Kao, Ping-Hue Huang |
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