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Number 1 · April 2003
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Table of Contents
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Tenth International RETRAN Conference Overview: RETRAN's Role in Supporting the Nuclear Industry's Vision
Volume 142 · Number 1 · April 2003 · Pages 3-9
Technical Paper · RETRAN

Lance J. Agee
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RETRAN-3D MOD003 Peach Bottom Turbine Trip 2 Multidimensional Kinetics Analysis Models and Results
Volume 142 · Number 1 · April 2003 · Pages 10-18
Technical Paper · RETRAN

Michitsugu Mori, Katsunori Ogura, Garry C. Gose, Jen-Ying Wu
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The Analysis of Pressurized Water Reactor and Boiling Water Reactor Reactivity Transients with CORETRAN and RETRAN-3D
Volume 142 · Number 1 · April 2003 · Pages 19-34
Technical Paper · RETRAN

Hakim Ferroukhi, Paul Coddington
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Application of the IBERDROLA RETRAN Licensing Methodology to the Confrentes BWR-6 110% Extended Power Uprate
Volume 142 · Number 1 · April 2003 · Pages 35-46
Technical Paper · RETRAN

Rafael de la Fuente, Javier Iglesias, Pablo G. Sedano, Pedro Mata
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Assessment of RETRAN-3D Boiling Models Against Experimental Subcooled Boiling Tube Data
Volume 142 · Number 1 · April 2003 · Pages 47-63
Technical Paper · RETRAN

Rafael Macian, Paul Coddington, Paul Stangroom
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Evaluation of the RETRAN-3D Wall Friction Models and Heat Transfer Coefficient Correlations
Volume 142 · Number 1 · April 2003 · Pages 64-76
Technical Paper · RETRAN

Craig E. Peterson, John G. Shatford, James F. Harrison, Lance J. Agee
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Thermal-Hydraulic Analysis of the Nuclear Power Engineering Corporation Containment Experiments with GOTHIC
Volume 142 · Number 1 · April 2003 · Pages 77-91
Technical Paper · RETRAN

Lawrence E. Wiles, Thomas L. George
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Number 2 · May 2003
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Table of Contents
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Using the OECD/NRC Pressurized Water Reactor Main Steam Line Break Benchmark to Study Current Numerical and Computational Issues of Coupled Calculations
Volume 142 · Number 2 · May 2003 · Pages 95-115
Technical Paper · OECD/NRC MSLB Benchmark

Kostadin N. Ivanov, Nadejda K. Todorova, Enrico Sartori
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Effects of Secondary Circuit Modeling on Results of Pressurized Water Reactor Main Steam Line Break Benchmark Calculations with New Coupled Code TRAB-3D/SMABRE
Volume 142 · Number 2 · May 2003 · Pages 116-123
Technical Paper · OECD/NRC MSLB Benchmark

Antti Daavittila, Anitta Hämäläinen, Riitta Kyrki-Rajamäki
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Analysis of the Pressurized Water Reactor Main Steam Line Break Benchmark by the Coupled Code System ATHLET-QUABOX/CUBBOX
Volume 142 · Number 2 · May 2003 · Pages 124-136
Technical Paper · OECD/NRC MSLB Benchmark

Siegfried Langenbuch, Klaus-Dieter Schmidt, Kiril Velkov
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Sensitivity Studies for Main Steam Line Break Exercises 2 and 3 with RELAP5/PANBOX
Volume 142 · Number 2 · May 2003 · Pages 137-145
Technical Paper · OECD/NRC MSLB Benchmark

Rainer Böer, Alfred Knoll
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Analyses of the OECD Main Steam Line Break Benchmark with the DYN3D and ATHLET Codes
Volume 142 · Number 2 · May 2003 · Pages 146-153
Technical Paper · OECD/NRC MSLB Benchmark

Ulrich Grundmann, Sören Kliem
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CEA-IRSN Participation in the Main Steam Line Break Benchmark
Volume 142 · Number 2 · May 2003 · Pages 154-165
Technical Paper · OECD/NRC MSLB Benchmark

E. Royer, E. Raimond, D. Caruge
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Analysis of the OECD Main Steam Line Break Benchmark Problem Using the Refined Core Thermal-Hydraulic Nodalization Feature of the MARS/MASTER Code
Volume 142 · Number 2 · May 2003 · Pages 166-179
Technical Paper · OECD/NRC MSLB Benchmark

Han Gyu Joo, Jae-Jun Jeong, Byung-Oh Cho, Won Jae Lee, Sung Quun Zee
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Three Mile Island Unit 1 Main Steam Line Break Three-Dimensional Neutronics/Thermal-Hydraulics Analysis: Application of Different Coupled Codes
Volume 142 · Number 2 · May 2003 · Pages 180-204
Technical Paper · OECD/NRC MSLB Benchmark

Francesco D'Auria, José Luis Gago Moreno, Giorgio Maria Galassi, Davor Grgic, Antonino Spadoni
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Number 3 · June 2003
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Table of Contents
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Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTRÉE
Volume 142 · Number 3 · June 2003 · Pages 205-229
Technical Paper · Fission Reactors

Akitoshi Hotta, Takafumi Anegawa, Takashi Hara, Hisashi Ninokata
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The Neutronics Design and Analysis of a 200-MW(electric) Simplified Boiling Water Reactor Core
Volume 142 · Number 3 · June 2003 · Pages 230-242
Technical Paper · Fission Reactors

Daniel R. Tinkler, Thomas J. Downar
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Basic Considerations on Defining Safety Goals
Volume 142 · Number 3 · June 2003 · Pages 243-249
Technical Paper · Reactor Safety

Tadakuni Hakata
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Investigation of Irradiation Behavior of SiC-Coated Fuel Particle at Extended Burnup
Volume 142 · Number 3 · June 2003 · Pages 250-259
Technical Paper · Fuel Cycle and Management

Kazuhiro Sawa, Tsutomu Tobita
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Out-of-Pile Properties of Hyperstoichiometric (U0.45Pu0.55)C Fuel for the Fast Breeder Test Reactor
Volume 142 · Number 3 · June 2003 · Pages 260-269
Technical Paper · Fuel Cycle and Management

A. K. Sengupta, J. Banerjee, T. Jarvis, T. R. G. Kutty, K. Ravi, S. Majumdar
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Experimental and Numerical Investigations on Debris Bed Coolability in a Multidimensional and Homogeneous Configuration with Volumetric Heat Source
Volume 142 · Number 3 · June 2003 · Pages 270-282
Technical Paper · Thermal Hydraulics

Kresna Atkhen, Georges Berthoud
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Taming the Crud Problem: A Utility Perspective
Volume 142 · Number 3 · June 2003 · Pages 283-293
Technical Paper · Nuclear Plant Operations and Control

Yovan D. Lukic, Jeffrey S. Schmidt
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Study of the Consequences of Secondary Water Radiolysis Surrounding a Defective Canister
Volume 142 · Number 3 · June 2003 · Pages 294-305
Technical Paper · Radioisotopes

Jinsong Liu, Ivars Neretnieks, Bo H. E. Strömberg
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Heterogeneous Target to Reduce the Toxicity of Spallation Products in an Accelerator-Driven System
Volume 142 · Number 3 · June 2003 · Pages 306-317
Technical Paper · Accelerators

Alexey Yu. Stankovsky, Vladimir V. Artisyuk, Masaki Saito
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