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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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
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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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Latest News
Trump picks former N.Y. congressman for NNSA administrator
Williams
President Trump has selected Brandon Williams to head the Department of Energy’s National Nuclear Security Administration, pending confirmation by the U.S. Senate.
Williams is a former one-term congressman (R., N.Y.),from 2023 to the beginning of 2025. Prior to political office he served in the U.S. Navy. Williams’s run for office gained attention in 2022 when he defeated fellow navy veteran Francis Conole, a Democrat, but he lost the seat last November to Democrat John Mannion.
“I will be honored to lead the tremendous scientific and engineering talent at NNSA,” Williams said, thanking Trump, according to WSYR-TV in Syracuse, N.Y.
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Computational Fluid Dynamics and Thermal-Hydraulic Analyses of SLIMM Reactor Passive Decay Heat Removal by Natural Circulation of Ambient Air
Luis Palomino, Mohamed S. El-Genk
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 1-14
Technical Paper | doi.org/10.13182/NT15-102
Two-Dimensional Axisymmetric Thermostructural Analysis of APR1400 Reactor Vessel Lower Head for Full-Core Meltdown Accident
Hyo-Nam Kim, Ihn Namgung
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 15-28
Technical Paper | doi.org/10.13182/NT15-17
A Scaling Analysis for a Filtered Containment Venting System
Jin Ho Song, Hyun-Joung Jo, Kwang Soon Ha, Jaehoon Jung, Sang Mo An, Hwan Yeol Kim, S. T. Revankar
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 29-43
Technical Paper | doi.org/10.13182/NT15-128
Evaluation of Pulsed Sphere Time-of-Flight and Neutron Attenuation Experimental Benchmarks Using MCNP6’s Unstructured Mesh Capabilities
Joel A. Kulesza, Roger L. Martz
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 44-54
Technical Paper | doi.org/10.13182/NT15-121
Evaluation of the Kobayashi Analytical Benchmark Using MCNP6’s Unstructured Mesh Capabilities
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 55-70
Technical Paper | doi.org/10.13182/NT15-122
Research on an Alarm Method for Initial Loose Parts in a Nuclear Reactor Based on Fractal Theory
Li-Xian Fang, Sheng-Yan Lin, Fu Zeng, Chi-Hu Wang, Yong-Cheng Xie
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 71-78
Technical Paper | doi.org/10.13182/NT15-62
Measurement of Boron Concentration with the Serpentuator System
Jun Li, Xiao-Bin Tang, Long-Gang Gui, Yun Ge, Ying Chen, Da Chen
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 79-86
Technical Paper | doi.org/10.13182/NT15-72
Total Hemispherical Emissivity of Grade 91 Ferritic Alloy with Various Surface Conditions
Christopher B. Azmeh, Kyle L. Walton, Tushar K. Ghosh, Sudarshan K. Loyalka, Dabir S. Viswanath, Robert V. Tompson
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 87-97
Technical Paper | doi.org/10.13182/NT15-54
Fuel Assembly Oscillation-Induced Flow in Initially Stagnant Fluid
Noah A. Weichselbaum, Shadman Hussain, Morteza Rahimi-Abkenar, Majid T. Manzari, Philippe M. Bardet
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 98-104
Technical Note | doi.org/10.13182/NT15-93
Investigation of the Dual-Cooled Annular Fuel Effect on the Thermal Power Uprate in a VVER-1000 Nuclear Reactor
G. R. Ansarifar, M. H. Esteki, M. Zaidabadi
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 105-109
Technical Note | doi.org/10.13182/NT15-90
Metrics for the Technical Performance Evaluation of Light Water Reactor Accident-Tolerant Fuel
Shannon M. Bragg-Sitton, Michael Todosow, Robert Montgomery, Christopher R. Stanek, Rose Montgomery, W. Jon Carmack
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 111-123
Technical Paper | doi.org/10.13182/NT15-149
Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks
Kaushik Banerjee, Kevin R. Robb, Georgeta Radulescu, John M. Scaglione, John C. Wagner, Justin B. Clarity, Robert A. LeFebvre, Joshua L. Peterson
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 124-142
Technical Paper | doi.org/10.13182/NT15-112
Operations Optimization of Nuclear Hybrid Energy Systems
Jun Chen, Humberto E. Garcia, Jong Suk Kim, Shannon M. Bragg-Sitton
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 143-156
Technical Paper | doi.org/10.13182/NT15-130
CFD Analysis and Design of Detailed Target Configurations for an Accelerator-Driven Subcritical System
Adam Kraus, Elia Merzari, Tanju Sofu, Zhaopeng Zhong, Yousry Gohar
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 157-168
Technical Paper | doi.org/10.13182/NT15-99
Comparison of Wireless Sensor Network Routing Protocols Under Gamma Radiation for Nuclear and Space Applications
Michael Nishimura, Yu Liu, Liqian Li, Karen Colins
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 169-180
Technical Paper | doi.org/10.13182/NT15-159
Thermochemical Compatibility and Oxidation Resistance of Advanced LWR Fuel Cladding
T. M. Besmann, Y. Yamamoto, K. A. Unocic
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 181-191
Technical Paper | doi.org/10.13182/NT15-132
Iodine Atom Diffusion in SiC and Zirconium with First-Principles Calculations
Ruixuan Han, Liucheng Liu, Rui Tu, Wei Xiao, Yingying Li, Huailin Li, Dan Shao
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 192-203
Technical Paper | doi.org/10.13182/NT15-109
Corrosion of INCONEL Alloy 625 in Molten LiCl-Li2O-Li
Augustus Merwin, Dev Chidambaram
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 204-212
Technical Paper | doi.org/10.13182/NT15-126
Development of a Low-Temperature Irradiation Capsule for Research Reactor Materials at HANARO
Kee Nam Choo, Man Soon Cho, Sung Woo Yang, Byung Hyuk Jun, Myong Seop Kim
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 213-221
Technical Note | doi.org/10.13182/NT15-154
Design Summary of the Mark-I Pebble-Bed, Fluoride Salt–Cooled, High-Temperature Reactor Commercial Power Plant
Charalampos Andreades, Anselmo T. Cisneros, Jae Keun Choi, Alexandre Y. K. Chong, Massimiliano Fratoni, Sea Hong, Lakshana R. Huddar, Kathryn D. Huff, James Kendrick, David L. Krumwiede, Michael R. Laufer, Madicken Munk, Raluca O. Scarlat, Nicolas Zweibaum, Ehud Greenspan, Xin Wang, Per Peterson
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 223-238
Technical Paper | doi.org/10.13182/NT16-2
Observed Redox Potential Range of Li2BeF4 Using a Dynamic Reference Electrode
Brian Kelleher, Kieran Dolan, Mark Anderson, Kumar Sridharan
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 239-252
Technical Paper | doi.org/10.13182/NT15-140
Exchange Current Density and Diffusion Layer Thickness in Molten LiCl-KCl Eutectic: A Modeling Perspective for Pyroprocessing of Metal Fuels
Suddhasattwa Ghosh, Krishan Kumar, Aligati Venkatesh, P. Venkatesh, Bandi Prabhakara Reddy
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 253-272
Technical Paper | doi.org/10.13182/NT16-37
Nonjudgmental Dynamic Fuel Cycle Benchmarking
Anthony Michael Scopatz
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 273-287
Technical Paper | doi.org/10.13182/NT15-153
Challenging Fuel Cycle Modeling Assumptions: Facility and Time-Step Discretization Effects
Robert W. Carlsen, Paul P. H. Wilson
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 288-300
Technical Paper | doi.org/10.13182/NT15-138
Verification of Safety in Safety Critical Computer-Based Systems: A Case Study of Nuclear Power Plant System
Lalit Singh, Hitesh Rajput
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 301-309
Technical Paper | doi.org/10.13182/NT15-151
Fueling Study of a CANDU Reactor Using Fuels Containing Burnable Neutron Absorbers
Jason J. Song, Paul K. Chan, Hugues W. Bonin, Stéphane Paquette
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 310-328
Technical Paper | doi.org/10.13182/NT16-1
The Hydrogen Issue in the Initial Operation of a Filtered Containment Venting System
Young Su Na, Song-Won Cho, Kwang Soon Ha
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 329-334
Technical Paper | doi.org/10.13182/NT15-160
A Nuclear Renewable Oil Shale System for Economic Dispatchable Low-Carbon Electricity and Liquid Fuels
D. J. Curtis, C. W. Forsberg
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 335-352
Technical Paper | doi.org/10.13182/NT16-14
Using the Sound of Nuclear Energy
Steven Garrett, James Smith, Robert Smith, Brenden Heidrich, Michael Heibel
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 353-362
Technical Paper | doi.org/10.13182/NT16-8
The Gamma Atmospheric Dispersion Factor for Finite-Cloud Radiation Dose Computations
John N. Hamawi
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 363-370
Technical Note | doi.org/10.13182/NT16-18
