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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Radial Moment Calculations of Coupled Electron-Photon Beams
Brian C. Franke, Edward W. Larsen
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE02-A2242
Treatment of Boundary Conditions in Trajectory-Based Deterministic Transport Methods
Richard Sanchez, Li Mao, Simone Santandrea
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 23-50
Technical Paper | doi.org/10.13182/NSE140-23
An Asymptotic Study of Discretized Transport Equations in the Fokker-Planck Limit
Shawn D. Pautz, Marvin L. Adams
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 51-69
Technical Paper | doi.org/10.13182/NSE02-A2244
Application of Neutron Dosimetry Measurements in the Determination of Reactor Pressure Vessel Fluence
John F. Carew, Kai Hu
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 70-85
Technical Paper | doi.org/10.13182/NSE02-A2245
Fast Neutron-Induced Emission of Light Charged Particles on Aluminum (En = 25 to 55 MeV)
S. Benck, I. Slypen, J.-P. Meulders, V. Corcalciuc, M. B. Chadwick
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 86-95
Technical Paper | doi.org/10.13182/NSE02-A2246
Studies on Photon Interaction Around the K-Edge of Some Elements
M. L. Mallikarjuna, S. B. Appaji Gowda, S. Krishnaveni, R. Gowda, T. K. Umesh
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 96-102
Technical Paper | doi.org/10.13182/NSE02-A2247
Nuclear Model Calculations for the Excitation Functions of Neutron-Induced Reactions on 58Ni in the Energy Range up to 20 MeV
K. Gul
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 103-110
Technical Paper | doi.org/10.13182/NSE02-A2248
An Algorithm for Parallel Sn Sweeps on Unstructured Meshes
Shawn D. Pautz
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 111-136
Technical Paper | doi.org/10.13182/NSE02-1
Unified Nodal Method Formulation for Analytic Function Expansion Nodal Method Solution to Two-Group Diffusion Equations in Rectangular Geometry
Hyun Chul Lee, Chang Hyo Kim
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 137-151
Technical Paper | doi.org/10.13182/NSE02-A2250
Three-Dimensional Modeling of a Steam-Line Break in a Boiling Water Reactor
Hernan Tinoco
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 152-164
Technical Paper | doi.org/10.13182/NSE02-A2251
Fluid Mechanics of Taylor Bubbles and Slug Flows in Vertical Channels
Henryk Anglart, Michael Z. Podowski
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 165-171
Technical Paper | doi.org/10.13182/NSE02-A2252
Thermohydraulics Oscillations and Numerical Integration
D. Ginestar, G. Verdú, J. March-Leuba
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 172-180
Technical Paper | doi.org/10.13182/NSE02-A2253
Implementation of a Two-Phase Boiling Model into the RELAP5/MOD2 Computer Code to Predict Void Distribution in Low-Pressure Subcooled Boiling Flows
G. H. Yeoh, J. Y. Tu
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 181-188
Technical Note | doi.org/10.13182/NSE02-A2254
Neutron Flux Perturbations due to Infinite Plane Absorbers IV: The Exponential Flux Revisited
M. M. R. Williams
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 189-194
Technical Note | doi.org/10.13182/NSE02-A2255
High-Resolution Cross-Section Measurements for Production of the 0.478-MeV Gamma Ray from the 9Be(n,x)7Li Reaction for Neutron Energies Between 12 and 200 MeV with Insight into the 10Be Level Scheme
R. O. Nelson, A. Michaudon
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 195-204
Technical Paper | doi.org/10.13182/NSE02-A2256
Studies on Plutonium Burning in the Prototype Fast Breeder Reactor Monju
Udo Wehmann, Hidehito Kinjo, Takeshi Kageyama
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 205-222
Technical Paper | doi.org/10.13182/NSE02-A2257
The Fission Converter-Based Epithermal Neutron Irradiation Facility at the Massachusetts Institute of Technology Reactor
O. K. Harling, K. J. Riley, T. H. Newton, B. A. Wilson, J. A. Bernard, L-W. Hu, E. J. Fonteneau, P. T. Menadier, S. J. Ali, B. Sutharshan, G. E. Kohse, Y. Ostrovsky, P. W. Stahle, P. J. Binns, W. S. Kiger III, P. M. Busse
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 223-240
Technical Paper | doi.org/10.13182/NSE02-A2258
Analysis of Unplated Subcritical Experiments Using Fresh Fuel Assemblies
Michelle Pitts, Farzad Rahnema
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 241-266
Technical Paper | doi.org/10.13182/NSE02-A2259
Kinetics Calculation Under Space-Dependent Feedback in Analytic Function Expansion Nodal Method via Solution Decomposition and Galerkin Scheme
Do Sam Kim, Nam Zin Cho
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 267-284
Technical Paper | doi.org/10.13182/NSE02-A2260
High-Order Boundary Condition Perturbation Theory for the Neutron Transport Equation
Michael Scott McKinley, Farzad Rahnema
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 285-294
Technical Paper | doi.org/10.13182/NSE02-A2261
