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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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A Block Adaptive Mesh Refinement Algorithm for the Neutral Particle Transport Equation
Randal S. Baker
Nuclear Science and Engineering | Volume 141 | Number 1 | May 2002 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE02-A2262
The Effect of Random Geometry on the Criticality of a Multiplying System III: Three Dimensional Systems and Spherical Absorbers
M. M. R. Williams
Nuclear Science and Engineering | Volume 141 | Number 1 | May 2002 | Pages 13-31
Technical Paper | doi.org/10.13182/NSE02-A2263
Neutronics Investigations for the Lower Part of a Westinghouse SVEA-96+ Assembly
M. F. Murphy, A. Lüthi, R. Seiler, P. Grimm, O. Joneja, A. Meister, R. van Geemert, F. Jatuff, R. Brogli, R. Jacot-Guillarmod, T. Williams, S. Helmersson, R. Chawla
Nuclear Science and Engineering | Volume 141 | Number 1 | May 2002 | Pages 32-45
Technical Paper | doi.org/10.13182/NSE02-A2264
Adjoint and Generalized Adjoint Flux Calculations Using the Collision Probability Technique
T. Courau, G. Marleau
Nuclear Science and Engineering | Volume 141 | Number 1 | May 2002 | Pages 46-54
Technical Paper | doi.org/10.13182/NSE02-A2265
Secondary Light Charged Particle Emission from the Interaction of 25- to 65-MeV Neutrons on Silicon
S. Benck, I. Slypen, J.-P. Meulders, V. Corcalciuc
Nuclear Science and Engineering | Volume 141 | Number 1 | May 2002 | Pages 55-65
Technical Paper | doi.org/10.13182/NSE02-A2266
Development of Fast-Running Simulation Methodology Using Neural Networks for Load Follow Operation
Seung-Hwan Seong, Heui-Youn Park, Dong-Hoon Kim, Yong-Suk Suh, Seop Hur, In-Soo Koo, Un-Chul Lee, Jin-Wook Jang, Yong-Chul Shin
Nuclear Science and Engineering | Volume 141 | Number 1 | May 2002 | Pages 66-77
Technical Paper | doi.org/10.13182/NSE02-A2267
APMN: A Program for Automatically Searching Optimal Optical Potential Parameters in the E 300 MeV Energy Region
Qing-Biao Shen
Nuclear Science and Engineering | Volume 141 | Number 1 | May 2002 | Pages 78-84
Computer Code Abstract | doi.org/10.13182/NSE01-19CCA
Alternative Implementations of the Monte Carlo Power Method
R. N. Blomquist, E. M. Gelbard
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 85-100
Technical Paper | doi.org/10.13182/NSE01-30
Intergenerational Correlation in Monte Carlo k-Eigenvalue Calculation
Taro Ueki
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 101-110
Technical Paper | doi.org/10.13182/NSE141-101
A Mixed-Oxide Assembly Design for Rapid Disposition of Weapons Plutonium in Pressurized Water Reactors
Gustavo Alonso, Marvin L. Adams
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 111-128
Technical Paper | doi.org/10.13182/NSE02-A2271
Gamma-Ray Spectroscopy Measurements of Decay Heat in Spent Nuclear Fuel
P. Jansson, A. Håkansson, A. Bäcklin, S. Jacobsson
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 129-139
Technical Paper | doi.org/10.13182/NSE02-A2272
Measurements of High-Energy Neutrons Penetrated Through Concrete Shields Using Self-TOF, NE213, and Activation Detectors
M. Sasaki, E. Kim, T. Nunomiya, T. Nakamura, N. Nakao, T. Shibata, Y. Uwamino, S. Ito, A. Fukumura
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 140-153
Technical Paper | doi.org/10.13182/NSE02-A2273
Calculation and Analysis of Double-Differential Cross Sections for n + 209Bi Reaction
Yinlu Han, Zhengjun Zhang
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 154-164
Technical Paper | doi.org/10.13182/NSE02-A2274
Experimental Study of Energy Distribution in Double Photon Compton Scattering
R. Dewan, M. B. Saddi, B. S. Sandhu, B. Singh, B. S. Ghumman
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 165-170
Technical Paper | doi.org/10.13182/NSE02-A2275
The 234U(nth,f) Cross Section Revisited
Cyriel Wagemans, Jan Wagemans, Olivier Serot
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 171-173
Technical Note | doi.org/10.13182/NSE02-A2276
Neutron Spectrum Effects on Burnup, Reactivity, and Isotopics in UO2/H2O Lattices
Zhiwen Xu, Michael J. Driscoll, Mujid S. Kazimi
Nuclear Science and Engineering | Volume 141 | Number 3 | July 2002 | Pages 175-189
Technical Paper | doi.org/10.13182/NSE02-A2277
Object-Oriented Three-Dimensional Fine-Mesh Transport Calculation on Parallel/Distributed Environments for Advanced Reactor Core Analyses
Masahiro Tatsumi, Akio Yamamoto
Nuclear Science and Engineering | Volume 141 | Number 3 | July 2002 | Pages 190-217
Technical Paper | doi.org/10.13182/NSE02-A2278
A Variational Nodal Expansion Method for the Solution of Multigroup Neutron Diffusion Equations with Heterogeneous Nodes
Makoto Tsuiki, Sverre Hval
Nuclear Science and Engineering | Volume 141 | Number 3 | July 2002 | Pages 218-235
Technical Paper | doi.org/10.13182/NSE02-A2279
Fully Consistent Diffusion Synthetic Acceleration of Linear Discontinuous SN Transport Discretizations on Unstructured Tetrahedral Meshes
James S. Warsa, Todd A. Wareing, Jim E. Morel
Nuclear Science and Engineering | Volume 141 | Number 3 | July 2002 | Pages 236-251
Technical Paper | doi.org/10.13182/NSE141-236
The Evaluation of Radiation Transport Forward-Adjoint Flux Integrals Using Monte Carlo Correlated Coupling Methods
S. N. Cramer
Nuclear Science and Engineering | Volume 141 | Number 3 | July 2002 | Pages 252-271
Technical Paper | doi.org/10.13182/NSE02-A2281
Cluster-Event Biasing in Monte Carlo Applications to Systems Reliability
Michael Khazen, Arie Dubi
Nuclear Science and Engineering | Volume 141 | Number 3 | July 2002 | Pages 272-287
Technical Paper | doi.org/10.13182/NSE02-A2282
