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Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2017.1317530
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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2017.1336028
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2017.1327253
