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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
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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