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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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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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Comparison of the Order of Approximation in Several Spatial Difference Schemes for the Discrete-Ordinates Transport Equation in One-Dimensional Plane Geometry
Suresh M. Lee, R. Vaidyanathan
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE80-A19287
Generalized Quasi-Static Method for Nuclear Reactor Space-Time Kinetics
J. Devooght, E. Mund
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 10-17
Technical Paper | doi.org/10.13182/NSE80-A19288
Transport of Thermal Neutrons in D2O in the Temperature Range 5 to 60°C Based on a New Scattering Kernel
R. M. Bansal, S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 18-29
Technical Paper | doi.org/10.13182/NSE80-A19289
Measurement of Cross Sections for the 63Cu(n, α)60Co Reaction from Threshold to 10 MeV
G. Winkler, Donald L. Smith, James W. Meadows
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 30-42
Technical Paper | doi.org/10.13182/NSE80-A19290
Cross-Section Measurement for the 52Cr(n,p)52V Reaction Near Threshold
Donald L. Smith, James W. Meadows
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 43-48
Technical Paper | doi.org/10.13182/NSE80-A19291
The Foil Thickness Correction in Measurements and the Discrepancy
J. W. Boldeman, J. Fréhaut
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 49-52
Technical Paper | doi.org/10.13182/NSE80-A19292
A Multiregion Calculation in the Theory of Neutron Diffusion
R. D. M. Garcia, C. E. Siewert
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 53-56
Technical Note | doi.org/10.13182/NSE80-A19293
Near-Equilibrium Measurements of Delayed Neutron Spectra from Fast Fission of Plutonium-240
Patrick J. Grant, Gene L. Woodruff
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 56-61
Technical Note | doi.org/10.13182/NSE80-A19294
Activation Cross Sections for 66Zn(n,p)66Cu
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 61-66
Technical Note | doi.org/10.13182/NSE80-A19295
Gamma-Ray Buildup Factors for Concrete Slab Shields Under Slant Incidence Conditions
E. M. Fournie, A. B. Chilton
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 66-69
Technical Note | doi.org/10.13182/NSE80-2
Measurements of Structural Material Capture to Uranium-235 Fission Rate Ratios in an Intermediate Spectrum Assembly
P. Azzoni, V. Benzi, A. Salomoni, P. L. Chiodi, C. Giuliani, R. Marvasi, S. Guardini, S. Tassan
Nuclear Science and Engineering | Volume 76 | Number 1 | October 1980 | Pages 70-77
Technical Note | doi.org/10.13182/NSE80-A19297
Investigation of Blowdown Problems with the Computer Code DRIX-2D
H. Mösinger
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 89-102
Technical Paper | doi.org/10.13182/NSE80-A19443
The Effect of Dispersion and Spheroidization Treatment of δ-ZrH2 on Creep and Corrosion Resistance of Zircaloy
Michiko Hamasaki, Shi-Chien Lin, Yii-Der Chuang
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 103-118
Technical Paper | doi.org/10.13182/NSE80-A19444
Experiments and Analyses of Neutron and Gamma-Ray Streaming in the Cavity-Duct System of a Fast Neutron Source Reactor
Yoshiaki Oka, Ichiroh Yanagisawa, Shigehiro An, Shun-ichi Miyasaka, Tomonori Hyodo
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 119-136
Technical Paper | doi.org/10.13182/NSE80-A19445
Parameter Determination and Application to Nuclear Model Calculations of Neutron-Induced Reactions on Yttrium and Zirconium Isotopes
E. D. Arthur
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 137-147
Technical Paper | doi.org/10.13182/NSE80-A19446
The Neutron Capture and Fission Cross Section of Americium-241 in the Energy Range from 10 to 250 keV
K. Wisshak, F. Käppeler
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 148-162
Technical Paper | doi.org/10.13182/NSE80-A19447
Delayed Neutron Signal Characterization in a Fast Reactor
Kenny C. Gross, Robert V. Strain
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 163-174
Technical Paper | doi.org/10.13182/NSE80-A19448
Plane Asymmetric Cell Lattices with Superimposed Small Buckling
T. Duracz
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 175-180
Technical Paper | doi.org/10.13182/NSE80-A19449
Treatment of Resonance Absorption in an Infinite Homogeneous Mixture Using Fourier Transforms
S. V. G. Menon, D. C. Sahni
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 181-197
Technical Paper | doi.org/10.13182/NSE80-A19450
Application of Biasing Techniques to the Contributon Monte Carlo Method
A. Dubi, S. A. W. Gerstl
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 198-217
Technical Paper | doi.org/10.13182/NSE80-A19451
A Nodal Green's Function Method for Multidimensional Neutron Diffusion Calculations
R. D. Lawrence, J. J. Dorning
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 218-231
Technical Paper | doi.org/10.13182/NSE80-A19452
The Determination of Coupled-Core-Reactor Kinetic Parameters Through Frequency Response
Yoshihiro Yamane, Kazuma Tanaka, Kojiro Nishina, Hajime Tamagawa, Seiji Shiroya
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 232-245
Technical Paper | doi.org/10.13182/NSE80-A19453
An Analysis of Why Single Pressure Two-Fluid Two-Phase Unequal Velocity Model Equations Are Not Globally Hyperbolic
Robert W. Lyczkowski
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 246-249
Technical Note | doi.org/10.13182/NSE80-A19454
A Method of Solution of the Transport Equation in Toroidal Geometry
J. K. Fletcher
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 249-255
Technical Note | doi.org/10.13182/NSE80-A19455
An Improved Single-Parameter Escape Probability Function
D. Kwiat
Nuclear Science and Engineering | Volume 76 | Number 2 | November 1980 | Pages 255-257
Technical Note | doi.org/10.13182/NSE76-255
Effective Diffusion Coefficients for Low Density Cylindrical Channels
J. L. Rowlands, C. R. Eaton
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 263-281
Technical Paper | doi.org/10.13182/NSE80-A21317
Fundamental Mode Decay Constants for Small Two- and Three-Dimensional Pulsed Neutron Moderator Assemblies
Vinod Kumar, D. C. Sahni
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 282-294
Technical Paper | doi.org/10.13182/NSE80-A21318
A Comparison of Maximum Likelihood and Other Estimators of Eigenvalues from Several Correlated Monte Carlo Samples
M. Beer
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 295-301
Technical Paper | doi.org/10.13182/NSE80-A21319
A Point Detector Scoring Method Compatible with Monte Carlo Transport Calculations of Specularly Reflected Particles
Hiromasa Iida, Yasushi Seki
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 302-307
Technical Paper | doi.org/10.13182/NSE80-A21320
A Recursive Monte Carlo Method for Estimating Importance Function Distributions in Deep-Penetration Problems
M. Goldstein, E. Greenspan
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 308-322
Technical Paper | doi.org/10.13182/NSE80-A21321
A Simple Formula for Calculation of Prompt Neutron Yield from Spontaneous Fission of Transuranics
H. L. Pai, D. G. Andrews
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 323-330
Technical Paper | doi.org/10.13182/NSE80-A21322
Cross-Section Measurement for the Reaction 103Rh(n,n')103mRh
A. Paulsen, R. Widera, R. Vaninbroukx, H. Liskien
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 331-335
Technical Paper | doi.org/10.13182/NSE80-A21323
Neutron Streaming in Pebble Beds
J. Lieberoth, A. Stojadinović
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 336-344
Technical Paper | doi.org/10.13182/NSE80-A21324
On the Solution of Linear Diffusion Problems in Media with Moving Boundaries
S. Bogado Leite, M. N. Özişik, K. Verghese
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 345-350
Technical Note | doi.org/10.13182/NSE80-A21325
An Evaluation of Different Methods for Space-Dependent Resonance Shielding of Cross Sections in Fast Reactors
J. V. Muralidhar Rao, S. M. Lee, M. L. Sharma
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 351-356
Technical Note | doi.org/10.13182/NSE80-A21326
Note on the Prompt-Fission-Neutron Spectra of Uranium-233 and -235 and Plutonium-239 and -240 Relative to That of Californium-252
A. Smith, P. Guenther, G. Winkler, R. McKnight
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 357-361
Technical Note | doi.org/10.13182/NSE80-A21327
Sodium Flow Blockage in Liquid-Metal Fast Breeder Reactors: Sweepout of a Planar Blockage
Douglas K. Warinner, S. C. Saxena
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 361-366
Technical Note | doi.org/10.13182/NSE80-A21328
Initial-Value Methods for a Simplified Subchannel Model of Thermal-Hydraulic Behavior
Paul Nelson, Charles H. Neil
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 366-370
Technical Note | doi.org/10.13182/NSE80-A21329