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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
Senate committee hears from energy secretary nominee Chris Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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Automated Weight Windows for Global Monte Carlo Particle Transport Calculations
Marc A. Cooper, Edward W. Larsen
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE00-34
An Adaptive Approach to Variational Nodal Diffusion Problems
Hui Zhang, E. E. Lewis
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 14-22
Technical Paper | doi.org/10.13182/NSE01-A2172
Composition Heterogeneity Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC) - I: Deterministic Analysis
Do Heon Kim, Hangbok Choi, Won Sik Yang, Jong Kyung Kim
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 23-37
Technical Paper | doi.org/10.13182/NSE01-A2173
Composition Heterogeneity Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC) - II: Statistical Analysis
Hangbok Choi
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 38-51
Technical Paper | doi.org/10.13182/NSE01-A2174
A Proposal for Benchmarking 235U Nuclear Data
A. dos Santos, R. Fuga, R. Jerez, A. Y. Abe, E. A. Filho
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 52-69
Technical Paper | doi.org/10.13182/NSE01-A2175
Treatment of External Levels in Neutron Resonance Fitting: Application to the Nonfissile Nuclide 52Cr
Fritz H. Fröhner, Olivier Bouland
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 70-88
Technical Paper | doi.org/10.13182/NSE01-A2176
Fragment Distribution Analysis of Proton-Induced Reactions with Intermediate Energy Using Quantum Molecular Dynamics Plus Fission Models
Sheng Fan, Zhu-Xiang Li, Yuheng Xiao
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 89-95
Technical Paper | doi.org/10.13182/NSE01-A2177
Application of Burnable Absorbers in an Accelerator-Driven System
Jan Wallenius, Kamil Tucek, Johan Carlsson, Waclaw Gudowski
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 96-106
Technical Note | doi.org/10.13182/NSE01-A2178
Interference of the Low-Energy Neutrons on Activation Cross-Section Measurement of the 186W(n, )187W Reaction
Guohui Zhang, Zhaomin Shi, Guoyou Tang, Jinxiang Chen, Guangzhi Liu, Hanlin Lu
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 107-110
Technical Note | doi.org/10.13182/NSE01-A2179
Analysis of Correlated Coupling of Monte Carlo Forward and Adjoint Histories
Taro Ueki, J. E. Hoogenboom, J. L. Kloosterman
Nuclear Science and Engineering | Volume 137 | Number 2 | February 2001 | Pages 117-145
Technical Paper | doi.org/10.13182/NSE01-A2180
New Photon Biasing Schemes for the "Once-More-Collided-Flux-Estimator" Method
N. Authier, J. P. Both, J. C. Nimal
Nuclear Science and Engineering | Volume 137 | Number 2 | February 2001 | Pages 146-155
Technical Paper | doi.org/10.13182/NSE01-A2181
An Application of Linear Superposition to Estimating Lattice-Physics Parameters
Jie Zheng, Tong Guo, G. Ivan Maldonado
Nuclear Science and Engineering | Volume 137 | Number 2 | February 2001 | Pages 156-172
Technical Paper | doi.org/10.13182/NSE01-A2182
Parallel Implementation of the Integral Transport Equation-Based Radiography Simulation Code
Feyzi Inanc, Bogdan Vasiliu, Dave Turner
Nuclear Science and Engineering | Volume 137 | Number 2 | February 2001 | Pages 173-182
Technical Paper | doi.org/10.13182/NSE01-A2183
Neutron Capture Cross Section of 232Th
K. Wisshak, F. Voss, F. Käppeler
Nuclear Science and Engineering | Volume 137 | Number 2 | February 2001 | Pages 183-193
Technical Paper | doi.org/10.13182/NSE01-A2184
Validation of the Characteristic Function Model for the Unresolved Resonance Region
N. Koyumdjieva, N. Janeva, K. Volev
Nuclear Science and Engineering | Volume 137 | Number 2 | February 2001 | Pages 194-205
Technical Paper | doi.org/10.13182/NSE01-A2185
Removal of Radioactive Cesium from Nuclear Waste Solutions with the Transition Metal Hexacyanoferrate Ion Exchanger CsTreat
R. Harjula, J. Lehto, A. Paajanen, L. Brodkin, E. Tusa
Nuclear Science and Engineering | Volume 137 | Number 2 | February 2001 | Pages 206-214
Technical Paper | doi.org/10.13182/NSE01-A2186
New Photon Exposure Buildup Factors
Omar Chibani
Nuclear Science and Engineering | Volume 137 | Number 2 | February 2001 | Pages 215-225
Technical Paper | doi.org/10.13182/NSE01-A2187
A Generalized Fokker-Planck Model for Transport of Collimated Beams
Anil K. Prinja, G. C. Pomraning
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 227-235
Technical Paper | doi.org/10.13182/NSE01-A2188
Generalized Fokker-Planck Approximations of Particle Transport with Highly Forward-Peaked Scattering
Christopher L. Leakeas, Edward W. Larsen
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 236-250
Technical Paper | doi.org/10.13182/NSE01-A2189
Multiple Scattering in Clouds: Insights from Three-Dimensional Diffusion/P1 Theory
Anthony B. Davis, Alexander Marshak
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 251-280
Technical Paper | doi.org/10.13182/NSE01-A2190
Variable Eddington Factors and Flux Limiters in Radiative Transfer
Bingjing Su
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 281-297
Technical Paper | doi.org/10.13182/NSE01-A2191
Discontinuous Finite Element Transport Solutions in Thick Diffusive Problems
Marvin L. Adams
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 298-333
Technical Paper | doi.org/10.13182/NSE00-41
Energy Transport in Matter with Rapidly Changing States
W. Höbel, B. Goel, A. L. Ni, H. Marten
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 334-351
Technical Paper | doi.org/10.13182/NSE01-A2193
Time-Dependent, One-Speed Transport via Generalized Functions
Noel R. Corngold
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 352-358
Technical Paper | doi.org/10.13182/NSE01-A2194
Exact PN Method Solutions
Norman J. McCormick
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 359-363
Technical Paper | doi.org/10.13182/NSE01-A2195
Classical Perturbation Theory for Monte Carlo Studies of System Reliability
Jeffrey D. Lewins
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 364-379
Technical Paper | doi.org/10.13182/NSE01-A2196
Studies on Nodal Integral Methods for the Convection-Diffusion Equation
E. P. E. Michael, J. Dorning, Rizwan-Uddin
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 380-399
Technical Paper | doi.org/10.13182/NSE137-380
From Fourier Transforms to Singular Eigenfunctions for Multigroup Transport
B. D. Ganapol
Nuclear Science and Engineering | Volume 137 | Number 3 | March 2001 | Pages 400-410
Technical Paper | doi.org/10.13182/NSE01-A2198
