ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Aug 2024
Jan 2024
Latest Journal Issues
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.
Jump to:
The Screened Rutherford Pencil Beam Problem with Heterogeneities
G. C. Pomraning
Nuclear Science and Engineering | Volume 136 | Number 1 | September 2000 | Pages 1-14
Technical Paper | doi.org/10.13182/NSE00-A2144
Higher-Order Boundary Condition Perturbation Theory for the Diffusion Approximation
Michael Scott McKinley, Farzad Rahnema
Nuclear Science and Engineering | Volume 136 | Number 1 | September 2000 | Pages 15-33
Technical Paper | doi.org/10.13182/NSE00-A2145
Some Aspects of Neutron Transport in Spatially Random Media
M. M. R. Williams
Nuclear Science and Engineering | Volume 136 | Number 1 | September 2000 | Pages 34-58
Technical Paper | doi.org/10.13182/NSE00-A2146
Adjoint Sensitivity Analysis of the RELAP5/MOD3.2 Two-Fluid Thermal-Hydraulic Code System—I: Theory
D. G. Cacuci, M. Ionescu-Bujor
Nuclear Science and Engineering | Volume 136 | Number 1 | September 2000 | Pages 59-84
Technical Paper | doi.org/10.13182/NSE136-59
Adjoint Sensitivity Analysis of the RELAP5/MOD3.2 Two-Fluid Thermal-Hydraulic Code System—II: Applications
M. Ionescu-Bujor, D. G. Cacuci
Nuclear Science and Engineering | Volume 136 | Number 1 | September 2000 | Pages 85-121
Technical Paper | doi.org/10.13182/NSE136-85
A Synthetic Acceleration for a Two-Dimensional Characteristic Method in Unstructured Meshes
Richard Sanchez, Abdelhuahed Chetaine
Nuclear Science and Engineering | Volume 136 | Number 1 | September 2000 | Pages 122-139
Technical Paper | doi.org/10.13182/NSE136-122
The Transport of Neutral Hydrogen Atoms in a Hydrogen Plasma
R. D. M. Garcia, C. E. Siewert
Nuclear Science and Engineering | Volume 136 | Number 1 | September 2000 | Pages 140-149
Technical Paper | doi.org/10.13182/NSE00-A2150
Development of Nonfertile and Evolutionary Mixed-Oxide Nuclear Fuels for Use in Existing Water Reactors
Stacey Eaton, Carl Beard, Kevin Ramsey, John Buksa, Ken Chidester
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 151-177
Technical Paper | doi.org/10.13182/NSE00-A2151
Split-Cell, Linear Characteristic Transport Method for Unstructured Tetrahedral Meshes
Kirk A. Mathews, Rodney L. Miller, Charles R. Brennan
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 178-201
Technical Paper | doi.org/10.13182/NSE00-A2152
Acceleration of Multidimensional Discrete Ordinates Methods Via Adjacent-Cell Preconditioners
Y. Y. Azmy
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 202-226
Technical Paper | doi.org/10.13182/NSE00-A2153
Load-Following Voltage Controller Design for a Static Space Nuclear Power System
Alexander G. Parlos, Fetiye O. Onbasioglu, John D. Metzger
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 227-246
Technical Paper | doi.org/10.13182/NSE00-A2154
Application of Temperature Parallel Simulated Annealing to Loading Pattern Optimizations of Pressurized Water Reactors
Akio Yamamoto, Hiroshi Hashimoto
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 247-257
Technical Paper | doi.org/10.13182/NSE00-A2155
Cross-Section Measurement for the 17O(n, p)17N Reaction by 14-MeV Neutrons
Y. Kasugai, Y. Ikeda, H. Sakane
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 258-264
Technical Paper | doi.org/10.13182/NSE00-A2156
Calculations for the Excitation Functions of Reactions Induced in 63Cu by Neutrons in the 1- to 20-MeV Energy Range
K. Gul
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 265-271
Technical Paper | doi.org/10.13182/NSE00-A2157
Definition of Subcriticality Using the Importance Function for the Production of Fission Neutrons
Keisuke Kobayashi, Kenji Nishihara
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 272-281
Technical Paper | doi.org/10.13182/NSE00-A2158
Uniform Gauss-Weight Quadratures for Discrete Ordinate Transport Calculations
John F. Carew, Kai Hu, Gabriel Zamonsky
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 282-293
Technical Paper | doi.org/10.13182/NSE99-96
Hybrid Skyshine Calculations for Complex Neutron and Gamma-Ray Sources
J. Kenneth Shultis
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 294-304
Technical Note | doi.org/10.13182/NSE00-A2160
A Quantitative Analysis of the Feynman- and Rossi-Alpha Formulas with Multiple Emission Sources
Z. F. Kuang, I. Pázsit
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 305-319
Technical Note | doi.org/10.13182/NSE00-A2161
Measurement and Analysis of Capture Reaction Rate of 237Np in Various Thermal Neutron Fields by Critical Assembly and Heavy Water Thermal Neutron Facility of Kyoto University
Tomohiko Iwasaki, Toshimitu Horiuchi, Daisuke Fujiwara, Hironobu Unesaki, Seiji Shiroya, Masatoshi Hayashi, Hiroshi Nakamura, Takanori Kitada, Nobuo Shinohara
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 321-339
Technical Paper | doi.org/10.13182/NSE00-A2162
Neutron Cross-Section Evaluations for 238U up to 150 MeV
A. V. Ignatyuk, V. P. Lunev, Yu. N. Shubin, E. V. Gai, N. N. Titarenko, A. Ventura, W. Gudowski
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 340-356
Technical Paper | doi.org/10.13182/NSE00-A2163
Photofission Cross Sections for 237Np in the Energy Interval from 5.27 to 10.83 MeV
L. P. Geraldo, R. Semmler, O. L. Gonçalez, J. Mesa, J. D. T. Arruda-Neto, F. Garcia, O. Rodriguez
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 357-362
Technical Paper | doi.org/10.13182/NSE00-A2164
Numerical and Experimental Study of Large Steam-Air Bubbles Injected in a Water Pool
Markus Meier, George Yadigaroglu, Michele Andreani
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 363-375
Technical Paper | doi.org/10.13182/NSE00-A2165
Modeling of Steam-Clad Interactions Under Severe Accident Conditions in Nuclear Power Light Water Reactors
M. A. Shinaishin, M. A. Abolfadl, A. S. Khedr, M. M. Kamel
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 376-387
Technical Paper | doi.org/10.13182/NSE00-A2166
The Third Basis Function Relevant to an Approximate Model of Neutral Particle Transport in Ducts
Roberto D. M. Garcia, Shizuca Ono, Wilson J. Vieira
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 388-398
Technical Paper | doi.org/10.13182/NSE00-1
Adaptive Importance Sampling with a Rapidly Varying Importance Function
Thomas E. Booth
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 399-408
Technical Note | doi.org/10.13182/NSE00-A2168
Semianalytical Procedures for Obtaining Low-Order Non-Equally-Probable Step-Function Representations in Multigroup Monte Carlo
Li Mao, J. C. Nimal
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 409-414
Technical Note | doi.org/10.13182/NSE00-A2169
Experimental Determination of the 236U(nth, f) Cross Section
Cyriel Wagemans, Olivier Serot, Peter Geltenbort, Oliver Zimmer
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 415-418
Technical Note | doi.org/10.13182/NSE00-A2170