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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2021)
February 9–11, 2021
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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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November 2020
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Former NRC chairs issue vaccine timeline recommendation to CDC
Five former chairmen of the U.S. Nuclear Regulatory Commission—Stephen Burns, Allison Macfarlane, Nils Diaz, Richard Meserve, and Dale Klein—signed a letter to José Romero, Arkansas health secretary and chair of the Centers for Disease Control and Prevention (CDC) immunization advisory committee, requesting that the advisory committee update its recommendation for COVID-19 vaccine allocation guidance for the energy workforce (including nuclear energy workers).
Currently, the CDC has four phases for the COVID-19 vaccine rollout. Those phases are numbered:
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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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.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 | dx.doi.org/10.13182/NSE09-85
