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Volume 199

Number 1 | Number 2 | Number 3

Number 1

Impact of Active Control on Passive Safety Response Characteristics of Sodium-Cooled Fast Reactors: I—Theoretical Background

Stefano Passerini, Roberto Ponciroli, Richard B. Vilim

Nuclear Technology / Volume 199 / Number 1 / July 2017 / Pages 1-15

Technical Paper / dx.doi.org/10.1080/00295450.2017.1326782

Impact of Active Control on Passive Safety Response Characteristics of Sodium-Cooled Fast Reactors: II—Model Implementation and Simulations

Roberto Ponciroli, Stefano Passerini, Richard B. Vilim

Nuclear Technology / Volume 199 / Number 1 / July 2017 / Pages 16-34

Technical Paper / dx.doi.org/10.1080/00295450.2017.1326783

Robust Control of Once-Through Canadian Supercritical Water-Cooled Reactors

Peiwei Sun, Ji Feng, Xianbao Yuan, Liang Zhao, Furong Liu

Nuclear Technology / Volume 199 / Number 1 / July 2017 / Pages 35-46

Technical Paper / dx.doi.org/10.1080/00295450.2017.1322396

Discrete Element Method–Based Investigations of Granular Flow in a Pebble Bed Reactor

Vaibhav Khane, Mahmoud M. Taha, Gary E. Mueller, Muthanna H. Al-Dahhan

Nuclear Technology / Volume 199 / Number 1 / July 2017 / Pages 47-66

Technical Paper / dx.doi.org/10.1080/00295450.2017.1324729

Neutronics and Safety Studies on a Research Reactor Concept for an Advanced Neutron Source

Zeyun Wu, Robert E. Williams, J. Michael Rowe, Thomas H. Newton, Sean O’Kelly

Nuclear Technology / Volume 199 / Number 1 / July 2017 / Pages 67-82

Technical Paper / dx.doi.org/10.1080/00295450.2017.1335146

Oxide-Metal Ratio Dependence of Central Void Formation of Mixed Oxide Fuel Irradiated in Fast Reactors

Yoshihisa Ikusawa, Koji Maeda, Masato Kato, Masayoshi Uno

Nuclear Technology / Volume 199 / Number 1 / July 2017 / Pages 83-95

Technical Paper / dx.doi.org/10.1080/00295450.2017.1314748

Study of the Interaction Between U3Si2/Al in Dispersion Plates at the End of the Fabrication Process

M. Mirandou, S. Aricó, R. Sanabria, S. Balart, D. Podestá, J. Fabro

Nuclear Technology / Volume 199 / Number 1 / July 2017 / Pages 96-102

Technical Paper / dx.doi.org/10.1080/00295450.2017.1323534

Thermal Conductivity of G-348 Isostatic Graphite

W. David Swank, Francisco I. Valentin, Masahiro Kawaji, Donald M. McEligot

Nuclear Technology / Volume 199 / Number 1 / July 2017 / Pages 103-109

Technical Note / dx.doi.org/10.1080/00295450.2017.1317530

Number 2

A Summary of the Department of Energy’s Advanced Demonstration and Test Reactor Options Study

D. Petti, R. Hill, J. Gehin, H. Gougar, G. Strydom, T. O’Connor, F. Heidet, J. Kinsey, C. Grandy, A. Qualls, N. Brown, J. Powers, E. Hoffman, D. Croson

Nuclear Technology / Volume 199 / Number 2 / August 2017 / Pages 111-128

Technical Paper / dx.doi.org/10.1080/00295450.2017.1336029

A New Modeling Technique to Analyze Safeguards Measurements in Large Systems

Nicolas Shugart, Jeffrey King

Nuclear Technology / Volume 199 / Number 2 / August 2017 / Pages 129-150

Technical Paper / dx.doi.org/10.1080/00295450.2017.1334435

Surrogates for Single-Phase Conjugate Heat Transfer Validation Experiments at Light Water Reactor Prototypical Conditions

Simon A. Clément, Philippe M. Bardet

Nuclear Technology / Volume 199 / Number 2 / August 2017 / Pages 151-173

Technical Paper / dx.doi.org/10.1080/00295450.2017.1327254

Numerical Investigation of Single-Phase Heat Transfer in a 2 × 2 Rod Bundle with Spacer Grids for a High Pressure Heat Transfer Facility

Xiaomeng Dong, Juliana P. Duarte, Zhijian Zhang, Michael L. Corradini, Zhaofei Tian, Guangliang Chen

Nuclear Technology / Volume 199 / Number 2 / August 2017 / Pages 174-186

Technical Paper / dx.doi.org/10.1080/00295450.2017.1326781

Advanced Burner Reactors with Breed-and-Burn Thorium Blankets for Improved Economics and Resource Utilization

Guanheng Zhang, Massimiliano Fratoni, Ehud Greenspan

Nuclear Technology / Volume 199 / Number 2 / August 2017 / Pages 187-218

Technical Paper / dx.doi.org/10.1080/00295450.2017.1337408

Fluidized Bed Chemical Vapor Deposition of Zirconium Nitride Films

Marie Y. Arrieta, Dennis D. Keiser, Jr., Delia Perez-Nunez, Sean M. McDeavitt

Nuclear Technology / Volume 199 / Number 2 / August 2017 / Pages 219-226

Technical Paper / dx.doi.org/10.1080/00295450.2017.1336028

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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