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Home / Publications / Journals / Nuclear Technology / Volume 148

Volume 148

Number 1 | Number 2 | Number 3

Number 1

Development of NSSS Thermal-Hydraulic Model for KNPEC-2 Simulator Using the Best-Estimate Code RETRAN-3D

Kyung-Doo Kim, Jae-Jun Jeong, Seung-Wook Lee, Myeong-Soo Lee, Jae-Seung Suh, Jin-Hyuk Hong, Yong-Kwan Lee

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 3-11

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3543

Modeling and Simulation of the ABWR with Transient Analyses for Validation of RETRAN-3D/MOD003

Michitsugu Mori

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 12-24

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3544

Benchmarking NSP Reactors with CORETRAN-01

Donald D. Hines, Rodney L. Grow, Lance J. Agee

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 25-34

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3545

Pretest Calculations of Phase A of ISP-42 (PANDA) Using the GOTHIC Containment Code and Comparison with the Experimental Results

Michele Andreani

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 35-47

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3546

Oconee Nuclear Power Station Main Steam Line Break Analysis for Steam Generator Tube Stress Evaluation

Jan S. Muransky, John G. Shatford, Craig E. Peterson, Gregg B. Swindlehurst

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 48-55

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3547

Development of Non-LOCA Safety Analysis Methodology with RETRAN-3D and VIPRE-01/K

Yo-Han Kim, Ae-Ju Cheong, Chang-Keun Yang

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 56-67

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3548

TIMCOAT: An Integrated Fuel Performance Model for Coated Particle Fuel

Jing Wang, Ronald G. Ballinger, Heather J. Maclean

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 68-96

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT04-A3549

Some Considerations on 242mAm Production in Thermal Reactors

Alessandra Cesana, Sara Tania Mongelli, Mario Terrani, Pietro Benetti, Elio Calligarich, Rinaldo Dolfini, Gian Luca Raselli

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 97-101

Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3550

Number 2

Independent Postclosure Performance Estimates of the Proposed Repository at Yucca Mountain

Sitakanta Mohanty, Richard Blake Codell

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 105-114

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3551

In-Drift Natural Convection Analysis of the Low-Temperature Operating Mode Design

Michael T. Itamura, Nicholas D. Francis, Jr., Stephen W. Webb, Darryl L. James

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 115-124

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3552

Multiscale Thermohydrologic Model Analyses of Heterogeneity and Thermal-Loading Factors for a Proposed Nuclear Waste Repository

Lee G. Glascoe, Thomas A. Buscheck, James Gansemer, Yunwei Sun, Kenrick Lee

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 125-137

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3553

The Impact of Preferential Flow on the Vaporization Barrier Above Waste Emplacement Drifts at Yucca Mountain, Nevada

Jens T. Birkholzer, Sumit Mukhopadhyay, Yvonne Y. W. Tsang

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 138-150

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3554

Biogeochemical Reactive Transport Model of the Redox Zone Experiment of the Äspö Hard Rock Laboratory in Sweden

Jorge Molinero-Huguet, F. Javier Samper-Calvete, Guoxiang Zhang, Changbing Yang

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 151-165

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3555

Corrosion Behavior of Waste Package and Drip Shield Materials

Gustavo A. Cragnolino, Darrell S. Dunn, C. Sean Brossia, Yi-Ming Pan, Osvaldo Pensado, Lietai Yang

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 166-173

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3556

Re-Evaluating Neptunium in Uranyl Phases Derived from Corroded Spent Fuel

Jeffrey A. Fortner, Robert J. Finch, A. Jeremy Kropf, James C. Cunnane

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 174-180

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3557

Congruent Release of Long-Lived Radionuclides from Multiple Canister Arrays

Daisuke Kawasaki, Joonhong Ahn, Paul L. Chambré, William G. Halsey

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 181-193

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3558

Role of the Bio- and Geosphere Interface on Migration Pathways for 135Cs and Ecological Effects

Anders Wörman, Björn Anders Dverstorp, Richard Andrew Klos, Shulan Xu

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 194-204

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3559

Alternative Igneous Source Term Model for Tephra Dispersal at the Yucca Mountain Repository

Richard Blake Codell

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 205-212

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3560

Smelters as Analogs for a Volcanic Eruption at Yucca Mountain

Benjamin Ross

Nuclear Technology / Volume 148 / Number 2 / November 2004 / Pages 213-219

Technical Paper / High-Level Radioactive Waste Disposal / dx.doi.org/10.13182/NT04-A3561

Number 3

Deterministic and Monte Carlo Neutron Transport Calculations of the Dounreay Fast Breeder Reactor

A. Kemal Ziver, Sabu Shahdatullah, Matthew D. Eaton, Cassiano R. E. de Oliviera, Ron T. Ackroyd, Adrian P. Umpleby, Christopher C. Pain, Antony J. H. Goddard, James Fitzpatrick

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 223-234

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT04-A3562

Validation of Simplified Evaluation Models for First Peak Power, Energy, and Total Fissions of a Criticality Accident in a Nuclear Fuel Processing Facility by TRACY Experiments

Yasushi Nomura, Hiroshi Okuno, Yoshinori Miyoshi

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 235-243

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT04-A3563

Plutonium Management in the Medium Term

Kevin Hesketh, Gerhard Schlosser, Dieter F. Porsch, Timm Wolf, Oliver Köberl, Benoit Lance, Rakesh Chawla, Jess C. Gehin, Ron Ellis, Sadao Uchikawa, Osamu Sato, Tsutomu Okubo, Hideaki Mineo, Toru Yamamoto, Yutaka Sagayama, Enrico Sartori

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 244-258

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3564

Development and Validation of the 3-D Computational Fluid Dynamics Model for CANDU-6 Moderator Temperature Predictions

Churl Yoon, Bo Wook Rhee, Byung-Joo Min

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 259-267

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3565

The Thermal Hydraulics of Tube Support Fouling in Nuclear Steam Generators

Helena E. C. Rummens, J. T. Rogers, C. W. Turner

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 268-286

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3566

Critical Heat Flux and Onset of Nucleate Boiling Tests in a Finned Rod Bundle

Hee Taek Chae, Jong Hark Park, Heonil Kim, Soon Heung Chang

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 287-293

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3567

Experimental Investigation of Natural-Circulation Flow Behavior Under Low-Power/Low-Pressure Conditions in the Large-Scale PANDA Facility

Olivier Auban, Domenico Paladino, Robert Zboray

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 294-312

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3568

Enhanced Natural Convection in a Metal Layer Cooled by Boiling Water

Jae-Seon Cho, Kune Y. Suh, Chang-Hyun Chung, Rae-Joon Park, Sang-Baik Kim

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 313-324

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3569

RELAP5/MOD3.2 Analysis of a VVER-1000 Reactor with UO2 Fuel and Mixed-Oxide Fuel

Yassin A. Hassan, Chun Fu

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 325-334

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3570

Code-Accuracy-Based Uncertainty Estimation (CABUE) Methodology for Large-Break Loss-of-Coolant Accidents

Sang-Yong Lee, Chang-Hwan Ban

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 335-347

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3571

A Strategic Recovery of Rare-Metal Fission Products in Spent Nuclear Fuel

Yuichi Sano, Yoshihiko Shinoda, Masaki Ozawa

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 348-357

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT04-A3572

Modeling of Colloid Transport Mechanisms Facilitating Migration of Radionuclides in Fractured Media

Shih-Hai Li, Hui-Ting Yang, Chun-Ping Jen

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 358-368

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT04-A3573

Analysis of Accidents at the Pakistan Research Reactor-1 Using Proposed Mixed-Fuel (HEU and LEU) Core

Ishtiaq H. Bokhari

Nuclear Technology / Volume 148 / Number 3 / December 2004 / Pages 369-376

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT04-A3574

 

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