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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
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Comparison of Spatial Discretization Methods for Solving the SN Equations Using a Three-Dimensional Method of Manufactured Solutions Benchmark Suite with Escalating Order of Nonsmoothness
Sebastian Schunert, Yousry Azmy
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 1-29
Technical Paper | doi.org/10.13182/NSE14-77
A New Equivalence Theory Method for Treating Doubly Heterogeneous Fuel—I: Theory
Mark L. Williams, Sooyoung Choi, Deokjung Lee
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 30-40
Technical Paper | doi.org/10.13182/NSE14-68
A New Equivalence Theory Method for Treating Doubly Heterogeneous Fuel—II: Verifications
Sooyoung Choi, Chidong Kong, Deokjung Lee, Mark L. Williams
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 41-57
Technical Paper | doi.org/10.13182/NSE14-72
Robust Statistical Error Estimation of Local Power Tallies in Monte Carlo Calculation of Light Water Reactor
Taro Ueki
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 58-68
Technical Paper | doi.org/10.13182/NSE14-54
A Hybrid Monte Carlo/Method-of-Characteristics Method for Efficient Neutron Transport Analysis
Hyunsuk Lee, Sooyoung Choi, Deokjung Lee
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 69-85
Technical Paper | doi.org/10.13182/NSE13-102
Neutron Capture Measurements and Resonance Parameters of Gadolinium
Y.-R. Kang, M. W. Lee, G. N. Kim, T.-I. Ro, Y. Danon, D. Williams, G. Leinweber, R. C. Block, D. P. Barry, M. J. Rapp
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 86-116
Technical Paper | doi.org/10.13182/NSE14-80
Plasma Temperature Inference From Deuterium-Tritium/Deuterium-Deuterium Neutron Discrimination
J. I. Katz
Nuclear Science and Engineering | Volume 180 | Number 1 | May 2015 | Pages 117-122
Technical Note | doi.org/10.13182/NSE14-81
A New Molybdenum Production Element for Implementation in TRIGA Reactors: Thermal-Hydraulic Characterization
W. R. Marcum, P. Y. Byfield, S. R. Reese
Nuclear Science and Engineering | Volume 180 | Number 2 | June 2015 | Pages 123-140
Technical Paper | doi.org/10.13182/NSE14-93
Study of Critical Heat Flux in Natural Convection–Cooled TRIGA Reactors with Single Annulus and Rod Bundle Geometries
Jun Yang, Michael Scott Greenwood, Matthew De Angelis, Michael Avery, Mark Anderson, Michael Corradini, James Matos, Floyd Dunn, Earl Feldman
Nuclear Science and Engineering | Volume 180 | Number 2 | June 2015 | Pages 141-153
Technical Paper | doi.org/10.13182/NSE14-45
Global Control of H-Infinity Multimodel System with Gap Metric and Self-Stability for Load-Following Nuclear Reactor Core
Gang Li
Nuclear Science and Engineering | Volume 180 | Number 2 | June 2015 | Pages 154-171
Technical Paper | doi.org/10.13182/NSE13-87
Determination of Turbulent Mixing Rate for Single-Phase Flow in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR
M. P. Sharma, A. K. Nayak
Nuclear Science and Engineering | Volume 180 | Number 2 | June 2015 | Pages 172-181
Technical Paper | doi.org/10.13182/NSE14-102
Validation of the Legendre Expansion of the Collision Law for Light Water Reactor Calculations
Ansar Calloo, Jean-François Vidal, Romain Le Tellier, Gérald Rimpault
Nuclear Science and Engineering | Volume 180 | Number 2 | June 2015 | Pages 182-198
Technical Paper | doi.org/10.13182/NSE14-57
Monte Carlo Fission Matrix Acceleration Method with Limited Inner Iteration
Liujun Pan, Ruihong Wang, Song Jiang
Nuclear Science and Engineering | Volume 180 | Number 2 | June 2015 | Pages 199-208
Technical Paper | doi.org/10.13182/NSE14-73
Temperature Majorant Cross Sections in Monte Carlo Neutron Tracking
Tuomas Viitanen, Jaakko Leppänen
Nuclear Science and Engineering | Volume 180 | Number 2 | June 2015 | Pages 209-223
Technical Paper | doi.org/10.13182/NSE14-46
The Infinite Medium Green’s Function of Monoenergetic Neutron Transport Theory via Fourier Transform
B. D. Ganapol
Nuclear Science and Engineering | Volume 180 | Number 2 | June 2015 | Pages 224-246
Technical Paper | doi.org/10.13182/NSE14-55
A Full-Core Resonance Self-Shielding Method Using a Continuous-Energy Quasi–One-Dimensional Slowing-Down Solution that Accounts for Temperature-Dependent Fuel Subregions and Resonance Interference
Yuxuan Liu, William Martin, Mark Williams, Kang-Seog Kim
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 247-272
Technical Paper | doi.org/10.13182/NSE14-65
Lagrange Discrete Ordinates: A New Angular Discretization for the Three-Dimensional Linear Boltzmann Equation
Cory D. Ahrens
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 273-285
Technical Paper | doi.org/10.13182/NSE14-76
Comparison of Neutronics-Depletion Coupling Schemes for Burnup Calculations—Continued Study
Aarno Isotalo
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 286-300
Technical Paper | doi.org/10.13182/NSE14-92
Effects of Bubble Injection on Heat Transfer from a Volumetrically Heated Water Pool
Geoffrey R. Bull, Jason O. Oakley, Michael L. Corradini
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 301-311
Technical Paper | doi.org/10.13182/NSE14-79
The Magnitude of Combined Physical and Chemical Explosions: A Mechanism for a Steam-Metal Chemical Explosion with Highly Reactive Metals
Robert E. Henry, Michael Epstein, Hans K. Fauske
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 312-334
Technical Paper | doi.org/10.13182/NSE14-90
The Effectiveness of Hydrogen Water Chemistry on Corrosion Mitigation in an Advanced Boiling Water Reactor
Mei-Ya Wang, Tsung-Kuang Yeh
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 335-340
Technical Paper | doi.org/10.13182/NSE14-97
Neutron Interactions with 3He Revisited—III: Neutron Cross Sections Between 24 and 30 MeV
M. Drosg
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 341-344
Technical Note | doi.org/10.13182/NSE14-96
Ambiguities in the Sensitivity and Uncertainty Analysis of Reactor Physics Problems Involving Constrained Quantities
Zoltán Perkó, Danny Lathouwers, Jan Leen Kloosterman, Tim H. J. J. van der Hagen
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 345-377
Technical Note | doi.org/10.13182/NSE14-17
