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The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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ANS Student Conference 2025
April 3–5, 2025
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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 Hybrid Transport-Diffusion Algorithm for Monte Carlo Radiation-Transport Simulations on Adaptive-Refinement Meshes in XY Geometry
Jeffery D. Densmore, Thomas M. Evans, Michael W. Buksas
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE159-01
Shielding Calculations for a Spent Fuel Storage Cask: A Comparison of Discrete Ordinates, Monte Carlo, and Hybrid Methods
R. J. Sheu, A. Y. Chen, Y.-W. H. Liu, S. H. Jiang
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 23-36
Technical Paper | doi.org/10.13182/NSE159-23
Efficient Generation of One-Group Cross Sections for Coupled Monte Carlo Depletion Calculations
E. Fridman, E. Shwageraus, A. Galperin
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 37-47
Technical Paper | doi.org/10.13182/NSE07-34
Use of Local Variation Method for Nuclear Design Calculations
A. I. Zhukov
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 48-55
Technical Paper | doi.org/10.13182/NSE159-48
Proliferation Resistance of Americium Originating from Spent Irradiated Reactor Fuel of Pressurized Water Reactors, Fast Reactors, and Accelerator-Driven Systems with Different Fuel Cycle Options
G. Kessler
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 56-82
Technical Paper | doi.org/10.13182/NSE159-56
New 237Np Burning Strategy in a Supercritical CO2-Cooled Fast Reactor Core Attaining Zero Burnup Reactivity Loss
Hoai Nam Tran, Yasuyoshi Kato
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 83-93
Technical Paper | doi.org/10.13182/NSE159-83
Subthreshold Fission Cross Section of 237Np
F. Tovesson, T. S. Hill
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 94-101
Technical Paper | doi.org/10.13182/NSE07-55
Spallation Product Distributions and Neutron Multiplicities for Accelerator-Driven System Using the CRISP Code
S. Anéfalos Pereira, A. Deppman, G. Silva, J. R. Maiorino, A. dos Santos, S. B. Duarte, O. A. P. Tavares, F. Garcia
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 102-105
Technical Note | doi.org/10.13182/NSE159-102
A Functional Monte Carlo Method for k-Eigenvalue Problems
Edward W. Larsen, Jinan Yang
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Pages 107-126
Technical Paper | doi.org/10.13182/NSE07-92
Linear and Quadratic Hexahedral Wavelets on the Sphere for Angular Discretizations of the Boltzmann Transport Equation
A. G. Buchan, C. C. Pain, M. D. Eaton, A. J. H. Goddard, R. P. Smedley-Stevenson
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Pages 127-152
Technical Paper | doi.org/10.13182/NSE159-127
Benchmark Calculation of WIMS/RFSP Against Physics Measurement Data of Wolsong Nuclear Power Plants
Hangbok Choi, Chang Je Park
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Pages 153-168
Technical Paper | doi.org/10.13182/NSE159-153
A Neutron Transport Benchmark in One-Dimensional Cylindrical Geometry: Revisited
B. D. Ganapol
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Pages 169-181
Technical Paper | doi.org/10.13182/NSE159-169
Measurements of Thermal Neutron Diffraction and Inelastic Scattering in Reactor-Grade Graphite
C. D. Bowman, D. C. Bowman, T. Hill, J. Long, A. P. Tonchev, W. Tornow, F. Trouw, Sven Vogel, R. L. Walter, S. Wender, V. Yuan
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Pages 182-198
Technical Paper | doi.org/10.13182/NSE159-182
Measurement of Neutron Capture Resonance Integrals on Bromine Isotopes
E. L. Dorval, M. A. Arribére, S. Ribeiro Guevara
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Pages 199-212
Technical Paper | doi.org/10.13182/NSE159-199
Modeling of High-Precision Neutron Nonelastic Cross Sections
F. S. Dietrich, J. D. Anderson, R. W. Bauer, S. M. Grimes, D. P. McNabb
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Pages 213-220
Technical Paper | doi.org/10.13182/NSE159-213
Identification of Optimal Number of Histogram Bars for Large Data Trends
Plamen V. Petkov
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Pages 221-227
Technical Note | doi.org/10.13182/NSE159-221
Nuclear Science and Engineering | Volume 159 | Number 2 | June 2008 | Page 228
Corrigendum | doi.org/10.13182/NSE159-228
Analytic Function Expansion Nodal Method for Multigroup Diffusion Equations in Cylindrical (r,,z) Geometry
Nam Zin Cho, Jaejun Lee
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 229-241
Technical Paper | doi.org/10.13182/NSE159-229
Finite Element Transport Using Wachspress Rational Basis Functions on Quadrilaterals in Diffusive Regions
Gregory G. Davidson, Todd S. Palmer
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 242-255
Technical Paper | doi.org/10.13182/NSE159-242
Efficient Subspace Methods-Based Algorithms for Performing Sensitivity, Uncertainty, and Adaptive Simulation of Large-Scale Computational Models
Hany S. Abdel-Khalik, Paul J. Turinsky, Matthew A. Jessee
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 256-272
Technical Paper | doi.org/10.13182/NSE159-256
A New Approach to Estimate Importance for Weight Window in Forward Monte Carlo Calculations
Isao Murata, Detlef Filges, Frank Goldenbaum
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 273-283
Technical Paper | doi.org/10.13182/NSE159-273
Research of Point Flux Estimation Method
Chunyan Li, Junli Li, Jianping Cheng, Zhen Wu, Lucheng Pei, Jiajin Fan
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 284-295
Technical Paper | doi.org/10.13182/NSE159-284
Purely Angular Effects of Photon Buildup Factors for Thin Shields of Lead, Iron, Aluminum, and Water
H. Omar Wooten, Donald J. Dudziak, Nolan E. Hertel, Drew E. Kornreich, Adam C. Davis
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 296-310
Technical Paper | doi.org/10.13182/NSE06-42
The Measurement of the Coolant Pressure Fluctuation and the Mechanical Vibration of the Equipment, and the Analysis of the Vibrodynamic Processes in a Nuclear Power Plant with a VVER-1000
M. Gholampour, K. N. Proskouriakov
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 311-320
Technical Paper | doi.org/10.13182/NSE159-311
Tritium-Charged Capacitor
A. Kavetsky, G. Yakubova, M. Sychov, Q. Lin, G. Walter, D. Chan, S. Yousaf, H. Socarras, J. Abrefah, K. Bower
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 321-329
Technical Paper | doi.org/10.13182/NSE159-321
A Quasi-Linear Implementation of High-Resolution Time Integration for the Pn Equations
Ryan G. McClarren, James Paul Holloway
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 330-337
Technical Note | doi.org/10.13182/NSE159-330
Two Media Method: An Alternative Methodology for the Measurement of Attenuation Coefficients of Irregularly Shaped Samples
Sukhpal Singh, Gurmel S. Mudahar, Ashok Kumar, Kulwant Singh Thind
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 338-345
Technical Note | doi.org/10.13182/NSE159-338
A Fission Chamber Measurement of the natB(d,n) Cross Section for Use in Neutron Detector Calibration
A. R. Di Lullo, T. N. Massey, S. M. Grimes, D. E. Carter, J. E. O'Donnell, D. Jacobs
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 346-350
Technical Note | doi.org/10.13182/NSE159-346TN
