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Volume 148

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

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

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

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

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

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

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

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

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

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

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

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

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

 
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