ANS / Publications / Journals / Nuclear Technology

Tenth International RETRAN Conference Overview: RETRAN's Role in Supporting the Nuclear Industry's Vision

Lance J. Agee

Nuclear Technology / Volume 142 / Number 1 / April 2003 / Pages 3-9

Technical Paper / RETRAN / dx.doi.org/10.13182/NT03-A3369

RETRAN-3D MOD003 Peach Bottom Turbine Trip 2 Multidimensional Kinetics Analysis Models and Results

Michitsugu Mori, Katsunori Ogura, Garry C. Gose, Jen-Ying Wu

Nuclear Technology / Volume 142 / Number 1 / April 2003 / Pages 10-18

Technical Paper / RETRAN / dx.doi.org/10.13182/NT03-A3370

The Analysis of Pressurized Water Reactor and Boiling Water Reactor Reactivity Transients with CORETRAN and RETRAN-3D

Hakim Ferroukhi, Paul Coddington

Nuclear Technology / Volume 142 / Number 1 / April 2003 / Pages 19-34

Technical Paper / RETRAN / dx.doi.org/10.13182/NT03-A3371

Application of the IBERDROLA RETRAN Licensing Methodology to the Confrentes BWR-6 110% Extended Power Uprate

Rafael de la Fuente, Javier Iglesias, Pablo G. Sedano, Pedro Mata

Nuclear Technology / Volume 142 / Number 1 / April 2003 / Pages 35-46

Technical Paper / RETRAN / dx.doi.org/10.13182/NT03-A3372

Assessment of RETRAN-3D Boiling Models Against Experimental Subcooled Boiling Tube Data

Rafael Macian, Paul Coddington, Paul Stangroom

Nuclear Technology / Volume 142 / Number 1 / April 2003 / Pages 47-63

Technical Paper / RETRAN / dx.doi.org/10.13182/NT03-A3373

Evaluation of the RETRAN-3D Wall Friction Models and Heat Transfer Coefficient Correlations

Craig E. Peterson, John G. Shatford, James F. Harrison, Lance J. Agee

Nuclear Technology / Volume 142 / Number 1 / April 2003 / Pages 64-76

Technical Paper / RETRAN / dx.doi.org/10.13182/NT03-A3374

Thermal-Hydraulic Analysis of the Nuclear Power Engineering Corporation Containment Experiments with GOTHIC

Lawrence E. Wiles, Thomas L. George

Nuclear Technology / Volume 142 / Number 1 / April 2003 / Pages 77-91

Technical Paper / RETRAN / dx.doi.org/10.13182/NT03-A3375

Using the OECD/NRC Pressurized Water Reactor Main Steam Line Break Benchmark to Study Current Numerical and Computational Issues of Coupled Calculations

Kostadin N. Ivanov, Nadejda K. Todorova, Enrico Sartori

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 95-115

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3376

Effects of Secondary Circuit Modeling on Results of Pressurized Water Reactor Main Steam Line Break Benchmark Calculations with New Coupled Code TRAB-3D/SMABRE

Antti Daavittila, Anitta Hämäläinen, Riitta Kyrki-Rajamäki

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 116-123

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3377

Analysis of the Pressurized Water Reactor Main Steam Line Break Benchmark by the Coupled Code System ATHLET-QUABOX/CUBBOX

Siegfried Langenbuch, Klaus-Dieter Schmidt, Kiril Velkov

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 124-136

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3378

Sensitivity Studies for Main Steam Line Break Exercises 2 and 3 with RELAP5/PANBOX

Rainer Böer, Alfred Knoll

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 137-145

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3379

Analyses of the OECD Main Steam Line Break Benchmark with the DYN3D and ATHLET Codes

Ulrich Grundmann, Sören Kliem

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 146-153

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3380

CEA-IRSN Participation in the Main Steam Line Break Benchmark

E. Royer, E. Raimond, D. Caruge

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 154-165

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3381

Analysis of the OECD Main Steam Line Break Benchmark Problem Using the Refined Core Thermal-Hydraulic Nodalization Feature of the MARS/MASTER Code

Han Gyu Joo, Jae-Jun Jeong, Byung-Oh Cho, Won Jae Lee, Sung Quun Zee

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 166-179

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT142-166

Three Mile Island Unit 1 Main Steam Line Break Three-Dimensional Neutronics/Thermal-Hydraulics Analysis: Application of Different Coupled Codes

Francesco D'Auria, José Luis Gago Moreno, Giorgio Maria Galassi, Davor Grgic, Antonino Spadoni

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 180-204

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3383

Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTRÉE

Akitoshi Hotta, Takafumi Anegawa, Takashi Hara, Hisashi Ninokata

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 205-229

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT03-A3384

The Neutronics Design and Analysis of a 200-MW(electric) Simplified Boiling Water Reactor Core

Daniel R. Tinkler, Thomas J. Downar

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 230-242

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT02-47

Basic Considerations on Defining Safety Goals

Tadakuni Hakata

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 243-249

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT03-A3386

Investigation of Irradiation Behavior of SiC-Coated Fuel Particle at Extended Burnup

Kazuhiro Sawa, Tsutomu Tobita

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 250-259

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3387

Out-of-Pile Properties of Hyperstoichiometric (U_0.45Pu_0.55)C Fuel for the Fast Breeder Test Reactor

A. K. Sengupta, J. Banerjee, T. Jarvis, T. R. G. Kutty, K. Ravi, S. Majumdar

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 260-269

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3388

Experimental and Numerical Investigations on Debris Bed Coolability in a Multidimensional and Homogeneous Configuration with Volumetric Heat Source

Kresna Atkhen, Georges Berthoud

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 270-282

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3389

Taming the Crud Problem: A Utility Perspective

Yovan D. Lukic, Jeffrey S. Schmidt

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 283-293

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT03-A3390

Study of the Consequences of Secondary Water Radiolysis Surrounding a Defective Canister

Jinsong Liu, Ivars Neretnieks, Bo H. E. Strömberg

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 294-305

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT03-A3391

Heterogeneous Target to Reduce the Toxicity of Spallation Products in an Accelerator-Driven System

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

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 306-317

Technical Paper / Accelerators / dx.doi.org/10.13182/NT03-A3392