Home / Publications / Journals / Nuclear Technology / Volume 179 / Number 3
Design Study to Increase Plutonium Conversion Ratio of HC-FLWR Core
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 309-322
Technical Paper / Fission Reactors/Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14165
Propagation of 235,236,238U and 239Pu Nuclear Data Uncertainties for a Typical PWR Fuel Element
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 323-338
Technical Paper / Fission Reactors/Fuel Cycle and Management / dx.doi.org/10.13182/NT11-61
Reactor Loose Part Damage Assessments on Steam Generator Tube Sheets
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 339-359
Technical Paper / Fission Reactors/Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT12-A14167
Evaluation of JSFR Key Technologies
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 360-373
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT179-360
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 374-381
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14169
Analysis of BR2 Loss-of-Flow Tests C and F
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 382-391
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A14170
An Algorithmic Approach for RELAP5/MOD3 Reactivity Insertion Analysis in Research Reactors
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 392-406
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A14171
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 407-416
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT12-A14172
In-Situ Creep Testing Capability for the Advanced Test Reactor
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 417-428
Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT12-A14173
Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 429-438
Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT11-5