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Volume 199

Number 3

Development of Streamlined Nuclear Safety Analysis Tool for Spent Nuclear Fuel Applications

R. A. Lefebvre, P. Miller, J. M. Scaglione, K. Banerjee, J. L. Peterson, G. Radulescu, K. R. Robb, A. B. Thompson, H. Liljenfeldt, J. P. Lefebvre

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

J. B. Clarity, K. Banerjee, H. K. Liljenfeldt, W. J. Marshall

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

Georgeta Radulescu, Kaushik Banerjee, Robert A. Lefebvre, L. Paul Miller, John M. Scaglione

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

Kevin R. Robb, Judith M. Cuta, L. Paul Miller

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

Georgeta Radulescu, Kaushik Banerjee, Robert A. Lefebvre, L. Paul Miller, John M. Scaglione

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

Josh Peterson, Bret van den Akker, Riley Cumberland, Paul Miller, Kaushik Banerjee

Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 310-319

Technical Paper / dx.doi.org/10.1080/00295450.2017.1318595

Additional Capability Being Developed from UNF-ST&DARDS Unified Database: System Analysis and Fuel Cycle Option Analysis

Josh Peterson, Chuck Olson, Jim St. Aubin, Brian Craig

Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 320-329

Technical Paper / dx.doi.org/10.1080/00295450.2017.1354551

COBRA-SFS Thermal-Hydraulic Analysis Code for Spent-Fuel Storage and Transportation Casks: Models and Methods

Thomas E. Michener, David R. Rector, Judith M. Cuta

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

Thomas E. Michener, David R. Rector, Judith M. Cuta

Nuclear Technology / Volume 199 / Number 3 / September 2017 / Pages 350-368

Technical Paper / dx.doi.org/10.1080/00295450.2017.1327253

 
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