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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
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Canada Deuterium Uranium Reactor Design Optimization Using Three-Dimensional Generalized Perturbation Theory
D. Rozon, M. Beaudet
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 1-20
Technical Paper | doi.org/10.13182/NSE92-A23919
Reconstruction of Pin Power and Burnup Characteristics from Nodal Calculations in Hexagonal-Z Geometry
W. S. Yang, P. J. Finck, H. Khalil
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 21-33
Technical Paper | doi.org/10.13182/NSE92-A23920
A Spectral Nodal Method for One-Group X,Y-Geometry Discrete Ordinates Problems
Ricardo C. De Barros, Edward W. Larsen
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 34-45
Technical Paper | doi.org/10.13182/NSE92-A23921
A Massively Parallel Discrete Ordinates Response Matrix Method for Neutron Transport
U. R. Hanebutte, E. E. Lewis
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 46-56
Technical Paper | doi.org/10.13182/NSE92-A23922
An Iterative Algorithm for Solving the Multidimensional Neutron Diffusion Nodal Method Equations on Parallel Computers
Bernadette L. Kirk, Yousry Y. Azmy
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 57-65
Technical Paper | doi.org/10.13182/NSE92-A23923
Estimation of Neutron Flux and Xenon Distributions via Observer-Based Control Theory
Young Ho Park, Nam Zin Cho
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 66-81
Technical Paper | doi.org/10.13182/NSE92-A23924
Ex-Vessel Releases of Radionuclides During Molten Core/Concrete Interactions in Severe Light Water Reactor Accidents
Min Lee, Jan Sea Wu
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 82-101
Technical Paper | doi.org/10.13182/NSE92-A23925
Time-Dependent Monte Carlo Calculations of the Oak Ridge Electron Linear Accelerator Target Neutron Spectrum
S. N. Cramer, F. G. Perey
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 102-111
Technical Paper | doi.org/10.13182/NSE92-A23926
An Extension of the Rigorous Pole Representation of Cross Sections for Reactor Applications
Richard N. Hwang
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 113-131
Technical Paper | doi.org/10.13182/NSE92-A23928
The Interaction of 1- to 20-MeV Neutrons with 238U
A. C. Merchant, P. E. Hodgson, H. R. Schelin
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 132-144
Technical Paper | doi.org/10.13182/NSE92-A23929
Diffusion Synthetic Acceleration of Discontinuous Finite Element Transport Iterations
Marvin L. Adams, William R. Martin
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 145-167
Technical Paper | doi.org/10.13182/NSE92-A23930
Three-Dimensional Variational Nodal Transport Methods for Cartesian, Triangular, and Hexagonal Criticality Calculations
C. B. Carrico, E. E. Lewis, G. Palmiotti
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 168-179
Technical Paper | doi.org/10.13182/NSE92-1
Domain Decomposition of a Two-Dimensional Sn Method
Ronald Mattis, Alireza Haghighat
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 180-196
Technical Paper | doi.org/10.13182/NSE92-A23932
Influence of Delayed Neutron Spectra on Fast Reactor Criticality
Edgar Kiefhaber
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 197-204
Technical Note | doi.org/10.13182/NSE92-A23933
Sensitivity Theory for the Closed Nuclear Fuel Cycle
H. B. Choi, T. J. Downar
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 205-213
Technical Note | doi.org/10.13182/NSE92-A23934
A Comparison of Models for Particle Transport Through Stochastic Mixtures
F.Malvagi, G. C. Pomraning
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 215-228
Technical Paper | doi.org/10.13182/NSE92-A23936
Probabilistic Reactor Dynamics —I: The Theory of Continuous Event Trees
J. Devooght, C. Smidts
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 229-240
Technical Paper | doi.org/10.13182/NSE92-A23937
Probabilistic Reactor Dynamics —II: A Monte Carlo Study of a Fast Reactor Transient
C. Smidts, J. Devooght
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 241-256
Technical Paper | doi.org/10.13182/NSE92-A23938
Analysis of Cluster Geometries Using the DP1 Approximation of the J± Technique
G. Marleau, A. Hebert
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 257-270
Technical Paper | doi.org/10.13182/NSE92-A23939
Applied Resonance Equivalence
M. Segev
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 271-278
Technical Paper | doi.org/10.13182/NSE91-51
Stability Improvement of the Alternating Direction Implicit Method for Two-Dimensional Space-Time Reactor Kinetics Applications
Gen-Shun Chen, John M. Christenson, Dow-Yung Yang
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 279-293
Technical Paper | doi.org/10.13182/NSE92-A23941
Gain-Scheduled Nonlinear Control of U-Tube Steam Generator Water Level
Sunil K. Menon, Alexander G. Parlos
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 294-308
Technical Paper | doi.org/10.13182/NSE92-A23942
Small-Angle Scattering Cross Sections of 14.8-MeV Neutrons for Iron, Nickel, and Chromium
Huiquan Qi, Hongbin Chen, Yingtang Chen, Qiankun Chen, Zhenpeng Chen, Zemin Chen
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 309-313
Technical Paper | doi.org/10.13182/NSE92-A23943
Cross-Section Measurement for 109Ag(n,2n),108mAg Reaction
Yongchang Wang, Junqian Yuan, Jingkang Yang, Huamin Wang, Yongqing Shui, Zhongliang Ren
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 314-316
Technical Paper | doi.org/10.13182/NSE92-A23944
Analytical Method for Processing Neutron Multigroup Transfer Cross Sections
R. Ofek, M. Segev
Nuclear Science and Engineering | Volume 111 | Number 4 | August 1992 | Pages 319-344
Technical Paper | doi.org/10.13182/NSE92-A15482
Contributon Slowing-Down Theory
Mark L. Williams, Harish Manohara
Nuclear Science and Engineering | Volume 111 | Number 4 | August 1992 | Pages 345-367
Technical Paper | doi.org/10.13182/NSE92-A15483
Product Yields of 235U, 238U, 237Np, and 239Pu by Photofission Reactions with 20-, 30-, and 60-MeV Bremsstrahlung
Takeshi Kase, Akira Yamadera, Takashi Nakamura, Seiichi Shibata, Ichiro Fujiwara
Nuclear Science and Engineering | Volume 111 | Number 4 | August 1992 | Pages 368-378
Technical Paper | doi.org/10.13182/NSE92-A15484
Fission Fragment Transport Effects on Heat Transfer in Fissioning Gases
Yoichi Watanabe, Jacob Appelbaum
Nuclear Science and Engineering | Volume 111 | Number 4 | August 1992 | Pages 379-390
Technical Paper | doi.org/10.13182/NSE92-A15485
Measurement of Neutron Activation Cross Sections of Energy up to 40 MeV Using Semimonoenergetic p-Be Neutrons
Yoshitomo Uwamino, Hiroshi Sugita, Yuhri Kondo, Takashi Nakamura
Nuclear Science and Engineering | Volume 111 | Number 4 | August 1992 | Pages 391-403
Technical Paper | doi.org/10.13182/NSE111-391
Evaluation of the Unresolved Resonance Range of 238U 4-+n, Part II: Differential Data Tests
F. H. Fröhner
Nuclear Science and Engineering | Volume 111 | Number 4 | August 1992 | Pages 404-414
Technical Paper | doi.org/10.13182/NSE92-A15487
High-Resolution Fission Cross-Section Measurements of 235U and 239Pu
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 111 | Number 4 | August 1992 | Pages 415-421
Technical Paper | doi.org/10.13182/NSE92-A15488
Six-Group Decomposition of Composite Delayed Neutron Spectra from 235U Fission
M. F. Villani, G. P. Couchell, M. H. Haghighi, D. J. Pullen, W. A. Schier
Nuclear Science and Engineering | Volume 111 | Number 4 | August 1992 | Pages 422-432
Technical Paper | doi.org/10.13182/NSE92-A15489
