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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
Senate committee hears from energy secretary nominee Chris Wright
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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Second-Order Generalized Perturbation Theory for Source-Driven Systems
E. Greenspan, D. Gilai, E. M. Oblow
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE68-1-1
The Probability Table Method and Correlated Data
S. Pearlstein
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 10-18
Technical Paper | doi.org/10.13182/NSE78-A27265
Monte Carlo Aspects of Contributons
A. Dubi, S. A. W. Gerstl, Donald J. Dudziak
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 19-30
Technical Paper | doi.org/10.13182/NSE78-A27266
Some Fundamental Relations Between Classical Problems of Transport Theory
P. Benoist
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 31-37
Technical Paper | doi.org/10.13182/NSE78-A27267
Differential Elastic and Inelastic Scattering of 7- to 15-MeV Neutrons from Beryllium
H. H. Hogue, P. L. Von Behren, D. H. Epperson, S. G. Glendinning, P. W. Lisowski, C. E. Nelson, H. W. Newson, F. O. Purser, W. Tornow, C. R. Gould, L. W. Seagondollar
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 38-42
Technical Paper | doi.org/10.13182/NSE78-A27268
Measurement of the Uranium-238 to Uranium-235 Fission Cross-Section Ratio for Neutron Energies Between 0.1 and 25 MeV
F. C. Difilippo, R. B. Perez, G. de Saussure, D. K. Olsen, R. W. Ingle
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 43-54
Technical Paper | doi.org/10.13182/NSE78-A27269
Analysis of Neutron Emission Spectra from 14-MeV Neutron Reactions
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 55-60
Technical Paper | doi.org/10.13182/NSE78-A27270
Optimum Burnup Distribution in a Continuously Fueled Reactor
A. L. Wight, P. Girouard
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 61-72
Technical Paper | doi.org/10.13182/NSE78-A27271
Transient Pressurization and Transport of a Two-Component Gas Within Interconnected Porosity of Solid Mixed-Oxide Fuel
J. R. Hofmann
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 73-90
Technical Paper | doi.org/10.13182/NSE78-A27272
Wigner-Wilkins Thermalization Revisited
J. Grzesik
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 91-94
Technical Note | doi.org/10.13182/NSE78-A27273
Sensitivity of Primary Knock-On Atom Spectra and Displacement per Atom Cross Sections to Different Secondary Neutron Energy and Angular Distributions and “In-Group” Weighting Schemes
T. A. Gabriel, B. L. Bishop
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 94-99
Technical Note | doi.org/10.13182/NSE78-A27274
Two-Media Problems in Two-Group Neutron Transport Theory
Yuji Ishiguro, Roberto D. M. Garcia
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 99-110
Technical Note | doi.org/10.13182/NSE78-A27275
Dynamic Measurements of a Nuclear Reactor Using Low-Peak-Factor Excitation Signals
J. O. Flower, S. C. Forge, N. G. Radcliffe, C. B. Roust
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 110-115
Technical Note | doi.org/10.13182/NSE78-A27276
Calculations of UH3 Critical Masses for Various Uranium Enrichments
Francis H. Lewis, Patrick D. Soran
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 116-125
Technical Note | doi.org/10.13182/NSE78-A27277
Multilevel Resonance Parameters of Plutonium-241
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 125-128
Technical Note | doi.org/10.13182/NSE78-A27278
Measurement of the Fission Cross Section of Plutonium-241 Relative to Uranium-235 for Neutron Energies from 1 keV to 30 MeV
G. W. Carlson, J. W. Behrens
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 128-132
Technical Note | doi.org/10.13182/NSE78-A27279
Best Values for the Cross Section of the Neutron Standard Reaction 10B(n,α1)7 Li in the Range from 0.1 to 2.0 MeV
Horst Liskien, Eric Wattecamps
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 132-137
Technical Note | doi.org/10.13182/NSE78-A27280
Thermal-Neutron Steady-State Spectra in Pure and Poisoned Light Water Assemblies
K. Swaminathan, S. P. Tewari, R. M. Bansal
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 137-140
Technical Note | doi.org/10.13182/NSE78-A27281
Self-Initialization of the RELAP4 Code Momentum Equation
R. C. Kern, M. T. Hsu
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 141-143
Technical Note | doi.org/10.13182/NSE78-A27282
Numerical Simulation of Hydrodynamic Impact Loads on Cylinders
B. D. Nichols, C. W. Hirt
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 143-148
Technical Note | doi.org/10.13182/NSE78-A27283
Two-Phase Flow Patterns with High-Pressure Water in a Heated Four-Rod Bundle
C. L. Williams, A. C. Peterson, Jr.
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 155-169
Technical Paper | doi.org/10.13182/NSE78-A27286
Neutron Flux Monitoring and Data Analysis for Neutron Standard Reaction Cross Sections
O. A. Wasson, R. A. Schrack, G. P. Lamaze
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 170-182
Technical Paper | doi.org/10.13182/NSE78-A27287
A New Measurement of the 6Li(n,α)T Cross Section
G. P. Lamaze, R. A. Schrack, O. A. Wasson
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 183-188
Technical Paper | doi.org/10.13182/NSE78-A27288
A Measurement of the 10B(n,αγ)7Li Cross Section in the keV Energy Region
R. A. Schrack, G. P. Lamaze, O. A. Wasson
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 189-196
Technical Paper | doi.org/10.13182/NSE78-A27289
Absolute Neutron Fission Cross Sections of 235U, 238U, and 239Pu at 13.9 and 14.6 MeV
M. Cancé, G. Grenier
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 197-203
Technical Paper | doi.org/10.13182/NSE78-A27290
Sputtering Calculations with the Discrete-Ordinates Method
T. J. Hoffman, H. L. Dodds, Jr., M. T. Robinson, D. K. Holmes
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 204-211
Technical Paper | doi.org/10.13182/NSE78-A27291
Cylindrical Source Shielding Equations Utilizing Compact Functions and Including Buildup
J. L. Kamphouse
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 212-217
Technical Note | doi.org/10.13182/NSE78-A27292
On Several Good Methods for Computing the Distortion Factor Relevant to a Foil Placed in an Exponentially Varying Flux
P. Benoist, V. C. Boffi, P. Grandjean, A. Kavenoky, V. G. Molinari, C. E. Siewert, G. Spiga
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 217-219
Technical Note | doi.org/10.13182/NSE78-A27293
Reactivity Prediction of Uniform PuO2-UO2-Fueled Lattices and Pu(NO3)4 Solutions in Light Water
P. Mohanakrishnan, H. C. Huria
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 220-226
Technical Note | doi.org/10.13182/NSE78-A27294
Neutron Wave Propagation Across an Absorption Discontinuity
Ashok Sadhwani, Ashok Kumar
Nuclear Science and Engineering | Volume 68 | Number 2 | November 1978 | Pages 226-230
Technical Note | doi.org/10.13182/NSE78-A27295
The One-Group Neutron Transport Equation and Angular Flux Separability
D. Shalitin, J. J. Wagschal, Y. Yeivin
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 243-248
Technical Paper | doi.org/10.13182/NSE78-A27303
Analytic Method for the Numerical Solution of the Integral Transport Equation for a Homogeneous Cylinder
Michael S. Milgram
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 249-269
Technical Paper | doi.org/10.13182/NSE78-A27304
Statistical Model Analysis of Spin Influence on the Deexcitation of Fission Fragments
D. P. Min, M. Martinot
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 270-280
Technical Paper | doi.org/10.13182/NSE78-A27305
Detailed Calculations in Energy and Space of Effective Neutron Resonance Cross Sections
José M. Aragonés
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 281-298
Technical Paper | doi.org/10.13182/NSE78-A27306
The Impact of Aging Mechanisms on Reactor Safety System Performance
E. Oelkers, W. W. Weaver
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 299-307
Technical Paper | doi.org/10.13182/NSE78-A27307
The Role of Rayleigh-Taylor Instabilities in Fuel-Coolant Interactions
Fred Cooper, John Dienes
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 308-321
Technical Paper | doi.org/10.13182/NSE78-A27308
Sensitivity Theory for Reactor Thermal-Hydraulics Problems
E. M. Oblow
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 322-337
Technical Paper | doi.org/10.13182/NSE78-A27309
Multidimensional Effects in Critical Two-Phase Flow
J. R. Travis, C. W. Hirt, W. C. Rivard
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 338-348
Technical Paper | doi.org/10.13182/NSE78-A27310
Possible Criticality of Protactinium-231
George C. Wu, Lawrence Ruby
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 349-351
Technical Note | doi.org/10.13182/NSE78-A27311
A Direct Technique for Unfolding Neutron Spectra from Activation Data
Hiroshi Sekimoto
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 351-356
Technical Note | doi.org/10.13182/NSE78-A27312
Effects of Nuclear Deformation on Neutron Total Cross Sections
L. Zuffi
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 356-357
Technical Note | doi.org/10.13182/NSE78-A27313
Measurements of the Total Neutron Cross Section of Uranium-233 Between 40 keV and 4.5 MeV
W. P. Poenitz, J. F. Whalen, P. Guenther, A. B. Smith
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 358-359
Technical Note | doi.org/10.13182/NSE78-A27314
The Fission Cross Sections of Plutonium-239 and Plutonium-242 Relative to Uranium-235 from 0.1 to 10 MeV
J. W. Meadows
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 360-363
Technical Note | doi.org/10.13182/NSE78-A27315
Best-Estimate Fuel Rod Modeling Techniques
D. A. Niebruegge, E. L. Tolman, C. W. Solbrig
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 363-368
Technical Note | doi.org/10.13182/NSE78-A27316
