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ANS > Publications > Journals > Nuclear Technology > Volume 142
Number 1  ·  Number 2  ·  Number 3
Number 1 · April 2003
Table of Contents
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
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
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
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
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
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
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
Number 2 · May 2003
Table of Contents
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
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
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
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
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
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
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
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
Number 3 · June 2003
Table of Contents
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
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
Basic Considerations on Defining Safety Goals
Volume 142 · Number 3 · June 2003 · Pages 243-249
Technical Paper · Reactor Safety

Tadakuni Hakata
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
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
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
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
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
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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