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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
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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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February 2023
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Nuclear power developments in China and the world
The development of human society and technology is closely correlated to the means of energy acquisition, utilization method, efficiency, and spectrum of applications. High quality of life and sustainable socioeconomic development require a sustainable and reliable energy supply. Wealth, health, food, water, infrastructure, education, and even life expectancy itself strongly correlate with the consumption of energy per capita. Having an adequate, reliable, affordable, eco-friendly, and sustainable supply of energy is becoming more crucial for economic development and improving human well-being.
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Equilibrium Core Composition Search Methodologies for Pebble Bed Reactors
Massimiliano Fratoni, Ehud Greenspan
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 1-16
Technical Paper | doi.org/10.13182/NSE09-66
Asymptotic Telegrapher's Equation (P1) Approximation for the Transport Equation
Shay I. Heizler
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 17-35
Technical Paper | doi.org/10.13182/NSE09-77
Manufactured Solutions in the Thick Diffusion Limit
James S. Warsa, Jeffery D. Densmore, Anil K. Prinja, Jim E. Morel
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 36-47
Technical Paper | doi.org/10.13182/NSE09-36
A Sensitivity Analysis of Nuclear Assembly Extinction Probabilities: Application to Reevaluated Fission Multiplicity Data
Scott D. Ramsey, Roy A. Axford
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 48-57
Technical Paper | doi.org/10.13182/NSE09-64
Shielding Electronic Devices from Monoenergetic 100-MeV Protons
Tai T. Pham, Mohamed S. El-Genk
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 58-72
Technical Note | doi.org/10.13182/NSE09-29TN
A Semianalytical Analysis of Transient Supercritical Assembly Extinction Probabilities
Scott D. Ramsey, Roy A. Axford, Gregory J. Hutchens
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 73-81
Technical Note | doi.org/10.13182/NSE09-63TN
Exponential Transform Acceleration Technique Using a Toroidal Importance Function for Monte Carlo Simulation of Neutral Particle Propagation
Cheikh M'Backé Diop
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 82-88
Technical Note | doi.org/10.13182/NSE09-56TN
Interpretation of PERLE Experiment for the Validation of Iron Nuclear Data Using Monte Carlo Calculations
C. Vaglio-Gaudard, A. Santamarina, P. Blaise, O. Litaize, A. Lyoussi, G. Noguère, J. M. Ruggieri, J. F. Vidal
Nuclear Science and Engineering | Volume 166 | Number 2 | October 2010 | Pages 89-106
Technical Paper | doi.org/10.13182/NSE09-91
Ex-Core Local Power Monitoring Using Neutron Streaming Pipes
Susumu Naito, Makoto Takemura, Shungo Sakurai, Mikio Izumi, Yasushi Goto, Yoshiji Karino
Nuclear Science and Engineering | Volume 166 | Number 2 | October 2010 | Pages 107-117
Technical Paper | doi.org/10.13182/NSE09-99
Tightly Coupled Multiphysics Algorithms for Pebble Bed Reactors
H. Park, D. A. Knoll, D. R. Gaston, R. C. Martineau
Nuclear Science and Engineering | Volume 166 | Number 2 | October 2010 | Pages 118-133
Technical Paper | doi.org/10.13182/NSE09-104
Spatial and Source Multiplication Effects on the Area Ratio Reactivity Determination Method in a Strongly Heterogeneous Subcritical System
C. Berglöf, M. Fernández-Ordóñez, D. Villamarín, V. Bécares, E. M. González-Romero, Victor Bournos, Ivan Serafimovich, Sergei Mazanik, Yurii Fokov
Nuclear Science and Engineering | Volume 166 | Number 2 | October 2010 | Pages 134-144
Technical Paper | doi.org/10.13182/NSE09-87
Diffusion Synthetic Acceleration for High-Order Discontinuous Finite Element SN Transport Schemes and Application to Locally Refined Unstructured Meshes
Yaqi Wang, Jean C. Ragusa
Nuclear Science and Engineering | Volume 166 | Number 2 | October 2010 | Pages 145-166
Technical Paper | doi.org/10.13182/NSE09-46
Investigation of Stochastic Radiation Transport Methods in Binary Random Heterogeneous Mixtures
D. R. Reinert, E. A. Schneider, S. R. F. Biegalski
Nuclear Science and Engineering | Volume 166 | Number 2 | October 2010 | Pages 167-174
Technical Paper | doi.org/10.13182/NSE09-45
Comments on Monte Carlo Probability of Initiation Estimates for Neutron Fission Chains
Thomas E. Booth
Nuclear Science and Engineering | Volume 166 | Number 2 | October 2010 | Pages 175-178
Technical Note | doi.org/10.13182/NSE09-101
An Integrated Methodology for Assessing Fire Simulation Code Uncertainty
Victor Ontiveros, Adrien Cartillier, Mohammad Modarres
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 179-201
Technical Paper | doi.org/10.13182/NSE10-05
Uncertainty Treatment for Level-2 Probabilistic Safety Analysis
A. Hoefer, G. Dirksen, J. Eyink, E.-M. Pauli
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 202-217
Technical Paper | doi.org/10.13182/NSE10-09
On the Degradation of Cell-Centered Diffusive Preconditioners for Accelerating SN Transport Calculations in the Periodic Horizontal Interface Configuration
Massimiliano Rosa, Yousry Y. Azmy, Jim E. Morel
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 218-238
Technical Paper | doi.org/10.13182/NSE09-69
A Discrete Generalized Multigroup Energy Expansion Theory
Lei Zhu, Benoit Forget
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 239-253
Technical Paper | doi.org/10.13182/NSE09-84
Uncertainty Quantification of Prompt Fission Neutron Spectrum for n(0.5 MeV) + 239Pu
P. Talou, T. Kawano, D. G. Madland, A. C. Kahler, D. K. Parsons, M. C. White, R. C. Little, M. B. Chadwick
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 254-266
Technical Paper | doi.org/10.13182/NSE09-10
New 56Fe Covariances for the JEFF3 File from the Feedback of Integral Benchmark Analysis
C. Vaglio-Gaudard, A. Santamarina, D. Bernard, G. Noguère, J. M. Ruggieri, J. F. Vidal, A. Lyoussi
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 267-275
Technical Paper | doi.org/10.13182/NSE09-103
Retroactive Generation of Covariance Matrix of Nuclear Model Parameters Using Marginalization Techniques
B. Habert, C. De Saint Jean, G. Noguere, L. Leal, Y. Rugama
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 276-287
Technical Paper | doi.org/10.13182/NSE09-85
