Number 1 | Number 2 | Number 3
Evolution of Sodium Technology R&D Actions Supporting French Liquid-Metal Fast Breeder Reactors
Nuclear Technology / Volume 150 / Number 1 / April 2005 / Pages 3-15
Technical Paper / Sodium Technology / dx.doi.org/10.13182/NT05-A3601
Nuclear Technology / Volume 150 / Number 1 / April 2005 / Pages 16-36
Technical Paper / Sodium Technology / dx.doi.org/10.13182/NT05-A3602
Lifetime Extension of the Phénix Plant
Nuclear Technology / Volume 150 / Number 1 / April 2005 / Pages 37-43
Technical Paper / Sodium Technology / dx.doi.org/10.13182/NT05-A3603
The Dounreay PFR Liquid-Metal Disposal Project
Nuclear Technology / Volume 150 / Number 1 / April 2005 / Pages 44-55
Technical Paper / Sodium Technology / dx.doi.org/10.13182/NT05-A3604
Upgrade of Cooling System Heat Removal Capacity of the Experimental Fast Reactor JOYO
Nuclear Technology / Volume 150 / Number 1 / April 2005 / Pages 56-66
Technical Paper / Sodium Technology / dx.doi.org/10.13182/NT05-A3605
Nuclear Technology / Volume 150 / Number 1 / April 2005 / Pages 67-78
Technical Paper / Sodium Technology / dx.doi.org/10.13182/NT05-A3606
Cleaning Cesium Radionuclides from BN-350 Primary Sodium
Nuclear Technology / Volume 150 / Number 1 / April 2005 / Pages 79-99
Technical Paper / Sodium Technology / dx.doi.org/10.13182/NT05-A3607
Nuclear Technology / Volume 150 / Number 1 / April 2005 / Pages 100-110
Technical Paper / Sodium Technology / dx.doi.org/10.13182/NT05-A3608
Nuclear Technology / Volume 150 / Number 1 / April 2005 / Pages 111-119
Technical Paper / Sodium Technology / dx.doi.org/10.13182/NT05-A3609
Nuclear Fuel Leasing, Recycling, and Proliferation: Modeling a Global View
Nuclear Technology / Volume 150 / Number 2 / May 2005 / Pages 121-131
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT05-A3610
Nuclear Technology / Volume 150 / Number 2 / May 2005 / Pages 132-144
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3611
Comparison of Severe Accident Results Among SCDAP/RELAP5, MAAP, and MELCOR Codes
Nuclear Technology / Volume 150 / Number 2 / May 2005 / Pages 145-152
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3612
Pyroprocessing of Light Water Reactor Spent Fuels Based on an Electrochemical Reduction Technology
Nuclear Technology / Volume 150 / Number 2 / May 2005 / Pages 153-161
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT05-A3613
A Subcritical, Gas-Cooled Fast Transmutation Reactor with a Fusion Neutron Source
Nuclear Technology / Volume 150 / Number 2 / May 2005 / Pages 162-188
Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT05-A3614
Incidence of High Nitrogen in Sintered Uranium Dioxide: A Case Study
Nuclear Technology / Volume 150 / Number 2 / May 2005 / Pages 189-195
Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT05-A3615
Detection and Localization of Money Bills Concealed Behind Wooden Walls Using Compton Scattering
Nuclear Technology / Volume 150 / Number 2 / May 2005 / Pages 196-202
Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT05-A3616
Nuclear Technology / Volume 150 / Number 2 / May 2005 / Pages 203-208
Technical Note / Materials for Nuclear Systems / dx.doi.org/10.13182/NT05-A3617
The Economics of Reprocessing Versus Direct Disposal of Spent Nuclear Fuel
Nuclear Technology / Volume 150 / Number 3 / June 2005 / Pages 209-230
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT05-A3618
Assessment of the RANS Turbulence Models for a Turbulent Flow and Heat Transfer in a Rod Bundle
Nuclear Technology / Volume 150 / Number 3 / June 2005 / Pages 231-250
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3619
Investigation of Containment Flooding Strategy for Mark-III Nuclear Power Plant with MAAP4
Nuclear Technology / Volume 150 / Number 3 / June 2005 / Pages 251-262
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3620
Nuclear Technology / Volume 150 / Number 3 / June 2005 / Pages 263-282
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3621
Improvements in Predicting Void Fraction in Subcooled Boiling
Nuclear Technology / Volume 150 / Number 3 / June 2005 / Pages 283-292
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3622
Design of a Software Sensor for Feedwater Flow Measurement Using a Fuzzy Inference System
Nuclear Technology / Volume 150 / Number 3 / June 2005 / Pages 293-302
Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT05-A3623
On the Radiolytic Decomposition of Colloidal Silver Iodide in Aqueous Suspension
Nuclear Technology / Volume 150 / Number 3 / June 2005 / Pages 303-314
Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT05-A3624
Nuclear Technology / Volume 150 / Number 3 / June 2005 / Pages 315-324
Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3625