Home / Publications / Journals / Nuclear Technology / Volume 199 / Number 3
Development of Streamlined Nuclear Safety Analysis Tool for Spent Nuclear Fuel Applications
Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 227-244
Technical Paper / dx.doi.org/10.1080/00295450.2017.1314747
As-Loaded Criticality Margin Assessment of Dual-Purpose Canisters Using UNF-ST&DARDS
Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 245-275
Technical Paper / dx.doi.org/10.1080/00295450.2017.1361250
Shielding Analysis Capability of UNF-ST&DARDS
Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 276-288
Technical Paper / dx.doi.org/10.1080/00295450.2017.1307643
Thermal Analysis Capability of UNF-ST&DARDS
Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 289-298
Technical Paper / dx.doi.org/10.1080/00295450.2017.1346446
Containment Analysis Capability of UNF-ST&DARDS
Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 299-309
Technical Paper / dx.doi.org/10.1080/00295450.2017.1348800
UNF-ST&DARDS Unified Database and the Automatic Document Generator
Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 310-319
Technical Paper / dx.doi.org/10.1080/00295450.2017.1318595
Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 320-329
Technical Paper / dx.doi.org/10.1080/00295450.2017.1354551
Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 330-349
Technical Paper / dx.doi.org/10.1080/00295450.2017.1305190
Validation of COBRA-SFS with Measured Temperature Data from Spent-Fuel Storage Casks
Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 350-368
Technical Paper / dx.doi.org/10.1080/00295450.2017.1327253