Home / Publications / Journals / Nuclear Technology / Volume 189 / Number 3
Representing Nuclear Criticality Excursion Experiment Data by an Artificial Neural Network
Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 219-240
Technical Paper / Criticality Safety / dx.doi.org/10.13182/NT14-44
Generation of Graphite Particles by Sliding Abrasion and Their Characterization
Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 241-257
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-25
Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 258-267
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-7
Turbine Bypass, Mass Inventory, and Mixed-Mode Generator Power Control of S-CO2 Recompression Cycle
Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 268-277
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-113
Conceptual Design of Passive Containment Cooling System for APR-1400 Using Multipod Heat Pipe
Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 278-293
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-121
Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 294-300
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT14-39
Microfluidic-Based Sample Chips for Radioactive Solutions
Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 301-311
Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT14-5
Radial Density Distribution in Irradiated FBR MOX Fuel Pellets
Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 312-317
Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT14-34