ANS / Publications / Journals / Nuclear Technology

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