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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Aug 2024
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Nuclear Science and Engineering
October 2024
Nuclear Technology
Fusion Science and Technology
August 2024
Latest News
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
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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