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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
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
Three nations, three ways to recycle plastic waste with nuclear technology
Plastic waste pollutes oceans, streams, and bloodstreams. Nations in Asia and the Pacific are working with the International Atomic Energy Agency through the Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative to tackle the problem. Launched in 2020, NUTEC Plastics is focused on using nuclear technology to both track the flow of microplastics and improve upstream plastic recycling before discarded plastic can enter the ecosystem. Irradiation could target hard-to-recycle plastics and the development of bio-based plastics, offering sustainable alternatives to conventional plastic products and building a “circular economy” for plastics, according to the IAEA.
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Solution to the Linear Time-Dependent Neutron Transport Equation with Time-Dependent Source and Cross Sections
W. L. Hendry
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 1-6
Technical Paper | doi.org/10.13182/NSE71-A20339
The Exact Probability Distribution of Reactor Neutron Noise
Andreas Szeless, Lawrence Ruby
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 7-13
Technical Paper | doi.org/10.13182/NSE71-A20340
Activation Measurements of the Doppler Effect in Uranium-238 and Thorium-232 at High Surface-to-Mass Values
R. N. Whitesel, R. Sher
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 14-24
Technical Paper | doi.org/10.13182/NSE71-A20341
Simultaneous Measurement of the Neutron Fission and Absorption Cross Sections of Plutonium-239 Over the Energy Region 0.02 eV to 30 keV
R. Gwin, L. W. Weston, G. de Saussure, R. W. Ingle, J. H. Todd, F. E. Gillespie, R. W. Hockenbury, R. C. Block
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 25-36
Technical Paper | doi.org/10.13182/NSE71-A20342
An Integral Measurement of Plutonium-239 and Uranium-233 Alpha
W. Y. Kato, R. J. Armani, R. P. Larsen, P. E. Moreland, L. A. Mountford, J. M. Gasidlo, R. J. Popek, C. D. Swanson
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 37-46
Technical Paper | doi.org/10.13182/NSE71-A20343
Photofission Cross Section of Plutonium-238 and Plutonium-239
Alvin Shapiro, Warren F. Stubbins
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 47-51
Technical Paper | doi.org/10.13182/NSE71-A20344
The Fuel Cycle Analysis System, REBUS
J. Hoover, G. K. Leaf, D. A. Meneley, P. M. Walker
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 52-65
Technical Paper | doi.org/10.13182/NSE71-1
Weighting and Biasing of a Monte Carlo Calculation for Very Deep Penetration of Radiation
Jeanne-Marie Lanore
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 66-72
Technical Paper | doi.org/10.13182/NSE71-A20346
A Model for Thermal and Radiation Stress and Strain in Viscoelastic, Orthotropic Cylinders, and Its Application to Borated-Graphite Absorbers
D. W. Stevens, O. M. Stansfield
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 73-85
Technical Paper | doi.org/10.13182/NSE71-A20347
An Observation on the Material Bucklings of the Multigroup Diffusion Equations
J. H. Marable, Melvin Tobias
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 86-87
Technical Note | doi.org/10.13182/NSE71-A20348
A Comparison of Measured and Calculated 239Pu, 235U, and 238U Integral Alpha Values in a Soft Spectrum Fast Critical Assembly
M. M. Bretscher, J. M. Gasidlo, W. C. Redman
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 87-94
Technical Note | doi.org/10.13182/NSE71-A20349
Effective Atomic Numbers for Photoelectric and Incoherent Scattering Processes of Gamma Rays
K. Siddappa, A. Khayyoom, K. Parthasaradhi, J. Rama Rao
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 94-97
Technical Note | doi.org/10.13182/NSE71-A20350
Optical Detection of Boiling in Pressurized Water Reactors
J. A. Bonnet, Jr., R. K. Osborn
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 97-99
Technical Note | doi.org/10.13182/NSE71-A20351
Anisothermal Effects During In-Pile Creep Testing of Uranium Dioxide
W. R. D. Wilson, J. S. Perrin
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 99-102
Technical Note | doi.org/10.13182/NSE71-A20352
A Method for Solving Time-Dependent Electron Transport Problems
Matthew C. Cordaro, Martin S. Zucker
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 107-116
Technical Paper | doi.org/10.13182/NSE71-A20878
Beam Enrichment by the Multilayered Neutron-Reflecting Conical Tube
T. Shimooke
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 117-125
Technical Paper | doi.org/10.13182/NSE71-A20879
Slow-Neutron Scattering by Light and Heavy Water
Yorio Gotoh, Hiroshi Takahashi
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 126-140
Technical Paper | doi.org/10.13182/NSE71-A20880
Neutron Spectra and Kinetic Properties in Fast Subcritical Assemblies Containing Uranium-235, Uranium-238, and Carbon
P. d'Oultremont, J. C. Young, J. M. Neill, C. A. Preskitt
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 141-155
Technical Paper | doi.org/10.13182/NSE71-A20881
The Degenerate Kernel Technique and Neutron Thermalization Calculations in Asymptotic Reactor Theory
Paul J. Turinsky, James J. Duderstadt
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 156-166
Technical Paper | doi.org/10.13182/NSE71-A20882
Applications of the Degenerate Kernel Technique to Thermal Neutron Spectra Calculations
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 167-181
Technical Paper | doi.org/10.13182/NSE71-A20883
P1 Blackness Theory for Infinite Cylinders
M. R. Mendelson, M. L. Storm
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 182-188
Technical Paper | doi.org/10.13182/NSE71-A20884
Solution of the Neutron Diffusion Equation by Space-Energy Factorization
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 189-198
Technical Paper | doi.org/10.13182/NSE71-A20885
Optimal Control of Nuclear Reactor Depletion
David C. Wade, William B. Terney
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 199-217
Technical Paper | doi.org/10.13182/NSE71-A20886
Radiation Effects on Superheating of Liquid Sodium
L. W. Deitrich
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 218-221
Technical Note | doi.org/10.13182/NSE71-A20887
Application of the Spectral Synthesis Method to the Analysis of Spatially Dependent Fast-Reactor Transients
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 221-226
Technical Note | doi.org/10.13182/NSE71-A20888
Analytic Solution to the Flat Flux Problem
William B. Terney
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 226-230
Technical Note | doi.org/10.13182/NSE71-A20889
Calculations of Thermal-Neutron Group Constants During Burnup of Light-Water-Moderated Lattices
M. Hron
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 230-232
Technical Note | doi.org/10.13182/NSE71-A20890
Integral Transport Theory Analysis of Central Reactivity Worth Measurements
P. E. McGrath, W. K. Foell
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 237-244
Technical Paper | doi.org/10.13182/NSE71-A19076
The Effectiveness of Acceleration Techniques for Iterative Methods in Transport Theory
W. H. Reed
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 245-254
Technical Paper | doi.org/10.13182/NSE71-A19077
Remedies for Ray Effects
K. D. Lathrop
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 255-268
Technical Paper | doi.org/10.13182/NSE45-03-255
Group Transfer Matrices and Their Relation to Basic Cross Section Data
M. Segev
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 269-278
Technical Paper | doi.org/10.13182/NSE71-A19079
Cross Sections in the Unresolved Resonance Region: Methods and Evaluation of Approximations
T. F. Heenan, C. R. Adkins
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 279-296
Technical Paper | doi.org/10.13182/NSE71-A19080
Neutron Inelastic Scattering Cross Sections for Iron, Nickel, Niobium, and Tantalum from Threshold to 1.8 MeV
V. C. Rogers, L. E. Beghian, F. M. Clikeman
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 297-307
Technical Paper | doi.org/10.13182/NSE71-A19081
Thermal-Neutron Diffusion Parameters in Water by the Poisoning Method
E. Martinho, M. M. Costa Paiva
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 308-313
Technical Paper | doi.org/10.13182/NSE71-A19082
Neutronic-Acoustic Detection of the Onset of Bulk Boiling in Liquid Sodium
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 314-320
Technical Paper | doi.org/10.13182/NSE71-A19083
Evaluation of Grain Shielding Factors for Coated Fuel Particles
P. Wälti
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 321-330
Technical Paper | doi.org/10.13182/NSE71-A19084
Matrix Reimann-Hilbert Problems Related to Neutron Transport Theory
E. E. Burniston, C. E. Siewert, P. Silvennoinen, P. F. Zweifel
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 331-332
Technical Note | doi.org/10.13182/NSE71-A19085
The Effect of Condensing the Spatial Mesh on the Accuracy of Fast Breeder Fuel-Cycle Analyses
Raymond E. Alcouffe, Thomas J. Hirons
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 333-335
Technical Note | doi.org/10.13182/NSE71-A19086
Kinetic Distortion in a TRIGA Reactor with an Asymmetric Reflector
Medhat M. El-Zeftawy, Lawrence Ruby
Nuclear Science and Engineering | Volume 45 | Number 3 | September 1971 | Pages 335-341
Technical Note | doi.org/10.13182/NSE71-2
