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Division Spotlight
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
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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Latest News
Site acquired for GLE laser enrichment plant
Global Laser Enrichment (GLE) has acquired a 665-acre parcel of land for its planned Paducah Laser Enrichment Facility (PLEF) in Kentucky.
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GENESIS: A Three-Dimensional Heterogeneous Transport Solver Based on the Legendre Polynomial Expansion of Angular Flux Method
Akio Yamamoto, Akinori Giho, Yuki Kato, Tomohiro Endo
Nuclear Science and Engineering | Volume 186 | Number 1 | April 2017 | Pages 1-22
Technical Paper | doi.org/10.1080/00295639.2016.1273002
Fourier Convergence Analysis of the Infinite Homogenous Multigroup Time-Dependent Boltzmann Transport Equation Using Discrete Ordinates Formulation
Ang Zhu, Yunlin Xu, Thomas Downar
Nuclear Science and Engineering | Volume 186 | Number 1 | April 2017 | Pages 23-37
Technical Paper | doi.org/10.1080/00295639.2016.1272387
The Effects of Oxidizing Species on Cobalt Buildup in a BWR Environment
Motomasa Fuse, Naoshi Usui, Nobuyuki Ohta, Yoshiteru Sato, Ryosuke Shimizu, Hideyuki Hosokawa, Tsuyoshi Ito, Yoichi Wada
Nuclear Science and Engineering | Volume 186 | Number 1 | April 2017 | Pages 38-47
Technical Paper | doi.org/10.1080/00295639.2016.1272385
Evaluation of Uranium-Based Fuels Augmented by Low Levels of Thorium for Near-Term Implementation in Pressure Tube Heavy Water Reactors
Ashlea V. Colton, Blair P. Bromley, Daniel Wojtaszek, Clifford Dugal
Nuclear Science and Engineering | Volume 186 | Number 1 | April 2017 | Pages 48-65
Technical Paper | doi.org/10.1080/00295639.2016.1273021
Illuminating Fuel Cycle Decision Drivers Using a Decision Analysis Framework
Lara M. Pierpoint
Nuclear Science and Engineering | Volume 186 | Number 1 | April 2017 | Pages 66-82
Technical Paper | doi.org/10.1080/00295639.2016.1272386
Facility Deployment Decisions Through Warp Optimization of Regressed Gaussian Processes
Anthony Michael Scopatz
Nuclear Science and Engineering | Volume 186 | Number 1 | April 2017 | Pages 83-97
Technical Paper | doi.org/10.1080/00295639.2016.1272384
Development of Bounding Burnup Axial Profiles for WWER-440 Spent Fuel Pool Burnup Credit Analysis
S. Bznuni, N. Baghdasaryan, A. Amirjanyan, G. Nazaryan, P. Kohut, J. Ramsey
Nuclear Science and Engineering | Volume 186 | Number 1 | April 2017 | Pages 98-102
Technical Paper | doi.org/10.1080/00295639.2016.1273012
A Computationally Viable Version of the PN Method for Spheres
R. D. M. Garcia, C. E. Siewert, J. R. Thomas Jr.
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 103-119
Technical Paper | doi.org/10.1080/00295639.2016.1273627
A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport for Pressurized Water Reactors
Tengfei Zhang, E. E. Lewis, M. A. Smith, W. S. Yang, Hongchun Wu
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 120-133
Technical Paper | doi.org/10.1080/00295639.2016.1273023
Evaluation of Pin-Cell Homogenization Techniques for PWR Pin-by-Pin Calculation
Bin Zhang, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Wei Shen
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 134-146
Technical Paper | doi.org/10.1080/00295639.2016.1273018
A New Method for Generating Probability Tables in the Unresolved Resonance Region
Andrew Holcomb, Luiz Leal, Farzad Rahnema, Dorothea Wiarda
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 147-155
Technical Paper | doi.org/10.1080/00295639.2016.1273632
Calculation and Evaluation for the n+51V Reaction
Hairui Guo, Yongli Xu, Yinlu Han, Qingbiao Shen, Tao Ye, Weili Sun
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 156-167
Technical Paper | doi.org/10.1080/00295639.2016.1273008
A Simple and Practical Correction Technique for Reactivity Worth of Short-Sized Samples Measured by Critical-Water-Level Method
Yasunori Kitamura, Masahiro Fukushima
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 168-179
Technical Paper | doi.org/10.1080/00295639.2016.1273017
Evaluation of Early Hydrogen Water Chemistry on Corrosion Mitigation in Boiling Water Reactors
Mei-Ya Wang, Tsung-Kuang Yeh
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 180-189
Technical Paper | doi.org/10.1080/00295639.2016.1273014
What Is the Real PFNS of 235U at Thermal Point?
N. V. Kornilov
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 190-198
Technical Paper | doi.org/10.1080/00295639.2016.1273625
Inverse Predictive Modeling of Radiation Transport Through Optically Thick Media in the Presence of Counting Uncertainties
Dan Gabriel Cacuci
Nuclear Science and Engineering | Volume 186 | Number 3 | June 2017 | Pages 199-223
Technical Paper | doi.org/10.1080/00295639.2017.1305244
Theoretical Convergence Rate Lower Bounds for Variants of Coarse Mesh Finite Difference to Accelerate Neutron Transport Calculations
Ang Zhu, Brendan Kochunas, Yunlin Xu, Michael Jarrett, Edward Larsen, Thomas Downar
Nuclear Science and Engineering | Volume 186 | Number 3 | June 2017 | Pages 224-238
Technical Paper | doi.org/10.1080/00295639.2017.1293408
A Neutron Transport Characteristics Method for 3D Axially Extruded Geometries Coupled with a Fine Group Self-Shielding Environment
S. Santandrea, D. Sciannandrone, R. Sanchez, L. Mao, L. Graziano
Nuclear Science and Engineering | Volume 186 | Number 3 | June 2017 | Pages 239-276
Technical Paper | doi.org/10.1080/00295639.2016.1273634
Neutron Time Interval Distributions with Background Neutrons
Manoj Prasad, Neal Snyderman, Sean Walston
Nuclear Science and Engineering | Volume 186 | Number 3 | June 2017 | Pages 277-292
Technical Paper | doi.org/10.1080/00295639.2016.1273620
A Simple Iterative Method for Compensating the Response Delay of a Self-Powered Neutron Detector
Qingmin Zhang, Zhigang Hu, Bangjie Deng, Mengxuan Xu, Yuhang Guo
Nuclear Science and Engineering | Volume 186 | Number 3 | June 2017 | Pages 293-302
Technical Paper | doi.org/10.1080/00295639.2016.1273619
