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Volume 127

Number 1 | Number 2 | Number 3

Number 1

Table of Contents

Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries

Luiz C. Leal, Otto W. Hermann, Stephen M. Bowman, Cecil V. Parks

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 1-23

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A2980

Drag Coefficients for Reactor Loose Parts

Liang Shi, J. Michael Doster, Charles W. Mayo

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 24-37

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2981

Modeling the Statics of a Natural-Circulation Boiling Water Reactor Loop

Haico V. Kok, Tim H. J. J. van der Hagen

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 38-48

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2982

Qualification of a Three-Dimensional Core Dynamics Analysis Program Coupled with a Detailed Mesh Division for Commercial Boiling Water Reactors-I

Yasunori Bessho, Takafumi Anegawa, Osamu Yokomizo, Yuichiro Yoshimoto, Masao Chaki, Motoo Aoyama, Takanori Fukahori

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 49-65

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2983

Natural Convection Heat Transfer with Crust Formation in the Molten Metal Pool

Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, Sang-Min Choi

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 66-80

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2984

Separation of Radioactive Strontium from Alkaline Nuclear Waste Solutions with the Highly Effective Ion Exchanger SrTreat

Jukka Lehto, Leena Brodkin, Risto Harjula, Esko Tusa

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 81-87

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A2985

Dose Rate Measurements and Calculation of TN-12/2 Packages

Hiroaki Taniuchi, Fumio Matsuda

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 88-101

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A2986

Empirical Steam Generator Water-Level Modeling Using Neural Networks

Chaung Lin, Tsung-Ming Lin

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 102-112

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A2987

Theoretical Calculations of Proton Reaction Cross Sections in a Lead Target with Energy E_p 300 MeV

Jinfeng Zhou, Qingbiao Shen, Xiuquan Sun

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 113-122

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT99-A2988

Uncertainty Analysis in DUPIC Fuel-Cycle Cost Using a Probabilistic Simulation Method

Won Il Ko, Jong Won Choi, Jae Sol Lee, Hyun Soo Park, Kun Jai Lee

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 123-140

Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT99-A2989

Number 2

Table of Contents

A MELCOR-Based Model to Calculate Vapor Natural Circulation in Pressurized Water Reactor High-Pressure Severe Accidents

Francisco Martín-Fuertes Hernández-Sonseca

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 141-150

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A2990

Modeling of the Rim Effect on Thermal Behavior of High-Burnup UO₂ Fuel

Byung-Ho Lee, Yang-Hyun Koo, Dong-Seong Sohn

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 151-159

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT99-A2991

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

Hyun Sik Park, Hee Cheon No

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 160-169

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2992

Core Damage Severity Evaluation for Pressurized Water Reactors by Use of Fuzzy Logic Algorithms

Anastasios Mironidis, Leon Lidofsky, George Grochowski, Lefteris Tsoukalas

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 170-185

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT99-A2993

Conceivable Limits for Thermal Reactor Spent-Fuel Recycling

David R. Kingdon, Vladimir A. Khotylev, Archie A. Harms, J. Eduard Hoogenboom

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 186-198

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT99-A2994

Matrix Diffusion of Simple Cations, Anions, and Neutral Species in Fractured Crystalline Rocks

Haruo Sato

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 199-211

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT127-199

Evaluation of the Effect of Temperature on Potassium Clinoptilolite Ion Exchange

David A. White, Andreas Nattkemper, Radu Ratautiu

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 212-217

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A2996

Design of the European Spallation Source Liquid-Metal Target Using Computational Fluid Dynamics

Trevor V. Dury, Brian L. Smith, Günter S. Bauer

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 218-232

Technical Paper / Accelerators / dx.doi.org/10.13182/NT99-A2997

An Electrocatalyzed Process for Leaching of Plutonium from Active Gauntlets and Subsequent Separation by Solvent Extraction

K. Venugopal Chetty, P. M. Mapara, A. G. Godbole, Rajendra Swarup

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 233-237

Technical Note / Reprocessing / dx.doi.org/10.13182/NT99-A2998

Number 3

Table of Contents

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

Gian Luigi Fiorini, Guy Marie Gautier, Yves Bergamaschi

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 239-258

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A2999

Feasibility Studies of a Soluble Boron-Free 900-MW(electric) PWR, Core Physics - I: Motivations, Assembly Design, and Core Control

Paul Thomet

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 259-266

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT127-259

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

Jean-Paul Deffain, Philippe Alexandre, Paul Thomet

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 267-286

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A3001

Hybrid Analysis of the Simplified Boiling Water Reactor Using RAMONA-4B and CASMO-3 Computer Codes

Gabriel F. Cuevas Vivas, Yassin A. Hassan

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 287-300

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A3002

Benchmark Calculations of the ESADA Single-Region Mixed-Oxide Critical Experiments

Hatice Akkurt, Naeem M. Abdurrahman

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 301-314

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A3003

Benchmark Calculations of the Saxton Plutonium Program Critical Experiments

Naeem M. Abdurrahman, Georgeta Radulescu, Igor Carron

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 315-331

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A3004

Behavior of a UF₆ Container During a Fire - I: Analysis and Phenomenological Interpretation of Tenerife Experimental Results

Eric Pinton, Bernard Duret, Georges Berthoud

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 332-351

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3005

Behavior of a UF₆ Container in a Fire - II: Modeling and Validation

Eric Pinton, Bernard Duret, Georges Berthoud

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 352-374

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3006

Uranium Dioxide Powder Preparation, Pressing, and Sintering for Optimum Yield

Palanki Balakrishna, Chandru K. Asnani, R. M. Kartha, K. Ramachandran, K. Sarat Babu, Vaidyanathan Ravichandran, Bhallamudi Narasimha Murty, Chaitanyamoy Ganguly

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 375-381

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A3007

Pressurized Water Reactor Coolant Pump Locked Rotor Analysis Methodology Using RETRAN-02 and FREY

Lainsu Kao, Ping-Hue Huang

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 382-388

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3008

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