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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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February 2025
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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Monte Carlo Electron Dose Calculations Using Discrete Scattering Angles and Discrete Energy Losses
Brian C. Franke, Anil K. Prinja
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE05-A2473
A Case Study in Manual and Automated Monte Carlo Variance Reduction with a Deep Penetration Reactor Shielding Problem
Herschel P. Smith, John C. Wagner
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 23-37
Technical Paper | doi.org/10.13182/NSE05-A2474
Stationarity Modeling and Informatics-Based Diagnostics in Monte Carlo Criticality Calculations
Taro Ueki, Forrest B. Brown
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 38-50
Technical Paper | doi.org/10.13182/NSE04-15
Development of the CPXSD Methodology for Generation of Fine-Group Libraries for Shielding Applications
F. Arzu Alpan, Alireza Haghighat
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 51-64
Technical Paper | doi.org/10.13182/NSE04-23
Comprehensive Cross-Section Database Development for Generalized Three-Dimensional Radiation Transport Codes
Thomas M. Miller, Lawrence W. Townsend
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 65-73
Technical Paper | doi.org/10.13182/NSE05-A2477
A Polynomial Form for Higher-Order Accurate Quantification of Perturbation Effects in Nuclear Systems
R. van Geemert, F. Tani
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 74-87
Technical Paper | doi.org/10.13182/NSE05-A2478
Some Features of Spatial Neutron Kinetics for Multiplying Systems
S. Dulla, P. Ravetto, M. M. Rostagno, G. Bianchini, M. Carta, A. D'Angelo
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 88-100
Technical Paper | doi.org/10.13182/NSE149-88
Impact of Radionuclide Physical Distribution on Brachytherapy Dosimetry Parameters
M. J. Rivard, B. L. Kirk, L. C. Leal
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 101-106
Technical Paper | doi.org/10.13182/NSE05-A2480
Modified Nodal Integral Method for the Three-Dimensional, Time-Dependent, Incompressible Navier-Stokes Equations
Fei Wang, Rizwan-uddin
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 107-114
Technical Paper | doi.org/10.13182/NSE149-107
Monte Carlo Modeling of High-Energy Film Radiography
Arthur C. Miller, Jr., Joseph L. Cochran, Vincent E. Lamberti
Nuclear Science and Engineering | Volume 149 | Number 2 | February 2005 | Pages 115-123
Technical Paper | doi.org/10.13182/NSE05-A2482
Dosimetry of Beta-Emitting Radionuclides at the Tissular Level Using Monte Carlo Methods
J. Coulot, F. Lavielle, A. Faggiano, N. Bellon, B. Aubert, M. Schlumberger, M. Ricard
Nuclear Science and Engineering | Volume 149 | Number 2 | February 2005 | Pages 124-130
Technical Paper | doi.org/10.13182/NSE05-A2483
Monte Carlo Criticality Calculations for a Pebble Bed Reactor with MCNP
Üner Çolak, Volkan Seker
Nuclear Science and Engineering | Volume 149 | Number 2 | February 2005 | Pages 131-137
Technical Paper | doi.org/10.13182/NSE04-17
Consistent Spatial Approximation of the Low-Order Quasi-Diffusion Equations on Coarse Grids
Dmitriy Y. Anistratov
Nuclear Science and Engineering | Volume 149 | Number 2 | February 2005 | Pages 138-161
Technical Paper | doi.org/10.13182/NSE05-A2485
Splitting Method for Solving the Coarse-Mesh Discretized Low-Order Quasi-Diffusion Equations
Hikaru Hiruta, Dmitriy Y. Anistratov, Marvin L. Adams
Nuclear Science and Engineering | Volume 149 | Number 2 | February 2005 | Pages 162-181
Technical Paper | doi.org/10.13182/NSE05-A2486
Capturing the Effects of Unlike Neighbors in Single-Assembly Calculations
Kevin T. Clarno, Marvin L. Adams
Nuclear Science and Engineering | Volume 149 | Number 2 | February 2005 | Pages 182-196
Technical Paper | doi.org/10.13182/NSE04-31
Fuel Assembly Calculations Using the Method of Discrete Ordinates
Andreas Pautz, Ulrich Hesse, Winfried Zwermann, Siegfried Langenbuch
Nuclear Science and Engineering | Volume 149 | Number 2 | February 2005 | Pages 197-210
Technical Paper | doi.org/10.13182/NSE05-A2488
Methodology of Internal Assessment of Uncertainty and Extension to Neutron Kinetics/Thermal-Hydraulics Coupled Codes
A. Petruzzi, F. D'Auria, W. Giannotti, K. Ivanov
Nuclear Science and Engineering | Volume 149 | Number 2 | February 2005 | Pages 211-236
Technical Paper | doi.org/10.13182/NSE04-26
Point Genetics: A New Concept to Assess Neutron Kinetics
R. Klein Meulekamp, J. C. Kuijper, M. Schikorr
Nuclear Science and Engineering | Volume 149 | Number 2 | February 2005 | Pages 237-245
Technical Paper | doi.org/10.13182/NSE05-A2490
Bounded Next-Event Estimation and Monte Carlo Forward-Adjoint Correlated Coupling
S. N. Cramer
Nuclear Science and Engineering | Volume 149 | Number 3 | March 2005 | Pages 247-258
Technical Paper | doi.org/10.13182/NSE05-A2491
Convergence Property of Response Matrix Method for Various Finite-Difference Formulations Used in the Nonlinear Acceleration Method
Akio Yamamoto
Nuclear Science and Engineering | Volume 149 | Number 3 | March 2005 | Pages 259-269
Technical Paper | doi.org/10.13182/NSE05-A2492
Detection of Antineutrinos for Nonproliferation
Michael Martin Nieto, A. C. Hayes, William B. Wilson, Corinne M. Teeter, William D. Stanbro
Nuclear Science and Engineering | Volume 149 | Number 3 | March 2005 | Pages 270-276
Technical Paper | doi.org/10.13182/NSE05-A2493
The Role of Fast Neutron-Induced Photon Production Data in the Search for Oil
M. C. Duijvestijn, A. Hogenbirk, A. J. Koning
Nuclear Science and Engineering | Volume 149 | Number 3 | March 2005 | Pages 277-287
Technical Paper | doi.org/10.13182/NSE05-A2494
Analysis of the Photoneutron Yield and Thermal Neutron Flux in an Unreflected Electron Accelerator-Driven Neutron Source
Gregory E. Dale, John M. Gahl
Nuclear Science and Engineering | Volume 149 | Number 3 | March 2005 | Pages 288-297
Technical Paper | doi.org/10.13182/NSE05-A2495
On the Performance of Point Kinetics for the Analysis of Accelerator-Driven Systems
M. Eriksson, J. E. Cahalan, W. S. Yang
Nuclear Science and Engineering | Volume 149 | Number 3 | March 2005 | Pages 298-311
Technical Paper | doi.org/10.13182/NSE03-103
Mitigation of SCC Initiation on BWR Core Internals by Means of Hydrogen Water Chemistry During Start-Up
Ayumi Abe, Hidehiro Tobita, Nobuaki Nagata, Koji Dozaki, Hideki Takiguchi
Nuclear Science and Engineering | Volume 149 | Number 3 | March 2005 | Pages 312-324
Technical Paper | doi.org/10.13182/NSE149-312
