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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
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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Performance Modeling of Parallel Algorithms for Solving Neutron Diffusion Problems
Y. Y. Azmy, B. L. Kirk
Nuclear Science and Engineering | Volume 120 | Number 1 | May 1995 | Pages 1-17
Technical Paper | doi.org/10.13182/NSE95-A24102
Physics Characteristics of Nuclear Power Systems with Reduced Long-Term Radioactivity Risk
M. Salvatores, I. Slessarev, M. Uematsu
Nuclear Science and Engineering | Volume 120 | Number 1 | May 1995 | Pages 18-39
Technical Paper | doi.org/10.13182/NSE95-A24103
Thick-Target Neutron Yield for Charged Particles
Kazuo Shin, Kagetomo Miyahara, Eiji Tanabe, Yoshitomo Uwamino
Nuclear Science and Engineering | Volume 120 | Number 1 | May 1995 | Pages 40-54
Technical Paper | doi.org/10.13182/NSE95-A24104
Inelastic Neutron Scattering by 235U and 238U Nuclei
N. V. Kornilov, A. B. Kagalenko
Nuclear Science and Engineering | Volume 120 | Number 1 | May 1995 | Pages 55-64
Technical Paper | doi.org/10.13182/NSE120-55
Behavior and Removal of Radionuclides Generated in the Cooling Water of a Proton Accelerator
C. Degueldre, A. Bilewicz, H. P. Alder
Nuclear Science and Engineering | Volume 120 | Number 1 | May 1995 | Pages 65-71
Technical Paper | doi.org/10.13182/NSE95-A24106
P1, P2 and Asymptotic Approximations for Stochastic Transport
Bingjing Su, G. C. Pomraning
Nuclear Science and Engineering | Volume 120 | Number 2 | June 1995 | Pages 75-90
Technical Paper | doi.org/10.13182/NSE95-A24109
Application of Piecewise Polynomial Collocation to the Unconstrained Quasi-Static Method for Canada Deuterium Uranium (CANDU) Reactor Space-Time Kinetics
A. Monier
Nuclear Science and Engineering | Volume 120 | Number 2 | June 1995 | Pages 91-101
Technical Paper | doi.org/10.13182/NSE95-A24110
A New MCNP Option: KCORR—The Use of the Correlated Sampling Method to Study Reactivity Effects Due to Changes of a Reactor Arrangement
Franz X. Gallmeier
Nuclear Science and Engineering | Volume 120 | Number 2 | June 1995 | Pages 102-109
Technical Paper | doi.org/10.13182/NSE95-A24111
One-Dimensional Diffusion Theory Kinetics in RELAP5
William K. Terry, David W. Nigg
Nuclear Science and Engineering | Volume 120 | Number 2 | June 1995 | Pages 110-123
Technical Paper | doi.org/10.13182/NSE95-A24112
Three-Dimensional Model of Vibration and Impacting of Instrument Tubes in a Boiling Water Reactor and Transfer from Mechanical to Neutron Noise
E. Laggiard, J. Runkel, D. Stegemann
Nuclear Science and Engineering | Volume 120 | Number 2 | June 1995 | Pages 124-135
Technical Paper | doi.org/10.13182/NSE95-A24113
Systematics in Differential Thick-Target Neutron Yields Parameterized by Moving Source Model
Nuclear Science and Engineering | Volume 120 | Number 2 | June 1995 | Pages 136-145
Technical Note | doi.org/10.13182/NSE95-A24114
A Diffusion-Synthetic Acceleration Technique for the Even-Parity Sn Equations with Anisotropic Scattering
J. E. Morel, J. M. McGhee
Nuclear Science and Engineering | Volume 120 | Number 3 | July 1995 | Pages 147-164
Technical Paper | doi.org/10.13182/NSE95-A24116
Exponential Characteristic Spatial Quadrature for Discrete Ordinates Radiation Transport with Rectangular Cells
Bryan Minor, Kirk Mathews
Nuclear Science and Engineering | Volume 120 | Number 3 | July 1995 | Pages 165-186
Technical Paper | doi.org/10.13182/NSE95-A24117
Anisotropic Scattering Treatment for the Neutron Transport Equation with Primal Finite Elements
B. Akherraz, C. Fedon-Magnaud, J. J. Lautard, R. Sanchez
Nuclear Science and Engineering | Volume 120 | Number 3 | July 1995 | Pages 187-198
Technical Paper | doi.org/10.13182/NSE95-A24118
Effects of Linear Polarization and Doppler Broadening on the Exposure Buildup Factors of Low-Energy Gamma Rays
Y. Namito, S. Ban, H. Hirayama
Nuclear Science and Engineering | Volume 120 | Number 3 | July 1995 | Pages 199-210
Technical Paper | doi.org/10.13182/NSE95-A24119
Approximating Model for Multilayer Gamma-Ray Buildup Factors by Transmission Matrix Method: Application to Point Isotropic Source Geometry
Kazuo Shin, Hideo Hirayama
Nuclear Science and Engineering | Volume 120 | Number 3 | July 1995 | Pages 211-222
Technical Paper | doi.org/10.13182/NSE95-A24120
Neutron Temperature Measurements in a Cryogenic Hydrogenous Moderator
Russell M. Ball, Gary S. Hoovler, Robert H. Lewis
Nuclear Science and Engineering | Volume 120 | Number 3 | July 1995 | Pages 223-230
Technical Paper | doi.org/10.13182/NSE95-A24121