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Home / Publications / Journals / Nuclear Technology / Volume 146 / Number 3

Volume 146

Number 3

Effect of Replacing Helium with a Liquid Metal in the Fuel-Cladding Gap on Fission Gas Release

Doonyapong Wongsawaeng, Donald R. Olander

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 211-220

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3500

A Simplified Approach for Evaluation of the Burnup Potential of Alternative Fuels

Stella Maris Oggianu, Hee Cheon No, Mujid S. Kazimi

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 221-229

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3501

WISE: A New Fuel Cycle Concept Based on a Mobile Fuel Reactor

Igor Slessarev, G. Palmiotti, M. Salvatores, V. Berthou

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 230-243

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3502

Investigating the Nonlinear Dynamics of Natural-Circulation, Boiling Two-Phase Flows

Robert Zboray, Wilhelmus J. M. de Kruijf, Tim H. J. J. van der Hagen, Rizwan-uddin

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 244-256

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3503

IIST Passive Core Cooling on Pressurizer Top Break

Tay-Jian Liu, Chien-Hsiung Lee

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 257-266

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3504

Multilevel Methodology in Parallel Computing Environment for Evaluating BWR Safety Parameters

Jorge Solís, Maria N. Avramova, Kostadin N. Ivanov

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 267-278

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3505

Experimental Validation of CFD Analyses for Estimating the Transport Fraction of LOCA-Generated Insulation Debris to ECCS Sump Screens

Arup K. Maji, Bruce Letellier, Kyle W. Ross, Daseri V. Rao, Luke Bartlein

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 279-289

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3506

A Fuzzy Modeling Approach to Road Transport with Application to a Case of Spent Nuclear Fuel Transport

Marzio Marseguerra, Enrico Zio, Mauro Bianchi

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 290-302

Technical Paper / Criticality of Nuclear Materials / dx.doi.org/10.13182/NT04-A3507

Radiation Shielding Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC)

Gyuhong Roh, Hangbok Choi

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 303-324

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT04-A3508

The Use of Molybdenum-Based Ceramic-Metal (CerMet) Fuel for the Actinide Management in LWRs

Klaas Bakker, Frodo C. Klaassen, Ronald P. C. Schram, Alfred Hogenbirk, Robin Klein Meulekamp, Arjan Bos, Hubert Rakhorst, Charles A. Mol

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 325-331

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT04-A3509

 

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