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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
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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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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On the Evaluation of Discrepant Scientific Data with Unrecognized Errors
Dan G. Cacuci, Mihaela Ionescu-Bujor
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 1-17
Technical Paper | doi.org/10.13182/NSE09-37A
Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation—I: Mathematical Framework
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 18-44
Technical Paper | doi.org/10.13182/NSE09-37B
Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation - II: Application to a Blowdown Benchmark Experiment
Alessandro Petruzzi, Dan G. Cacuci, Francesco D'Auria
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 45-100
Technical Paper | doi.org/10.13182/NSE09-37C
Scaled and Full-Size Three-Loop Reactor Vessel Simulation for Boron Dilution Studies Using Computational Fluid Dynamics
T. V. Dury, M. T. Dhotre
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 101-116
Technical Paper | doi.org/10.13182/NSE08-90
The 235U(n,f) Prompt Fission Neutron Spectrum at 100 K Input Neutron Energy
N. Kornilov, F.-J. Hambsch, I. Fabry, S. Oberstedt, T. Belgya, Z. Kis, L. Szentmiklosi, S. Simakov
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 117-127
Technical Paper | doi.org/10.13182/NSE09-25
Comments on “Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors”
Gray S. Chang
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 128-130
Letter to the Editor | doi.org/10.13182/NSE09-58L
Reply to “Comments on ‘Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors’”
Jan Dufek
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 130-131
Letter to the Editor | doi.org/10.13182/NSE09-58R
Nonlinear Weighted Flux Methods for Particle Transport Problems in Two-Dimensional Cartesian Geometry
Loren Roberts, Dmitriy Y. Anistratov
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 133-148
Technical Paper | doi.org/10.13182/NSE08-48
Asymptotic Diffusion-Limit Accuracy of Sn Angular Differencing Schemes
Teresa S. Bailey, Jim E. Morel, Jae H. Chang
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 149-169
Technical Paper | doi.org/10.13182/NSE08-66
Adaptive Three-Dimensional Monte Carlo Functional-Expansion Tallies
Brian C. Franke, Ronald P. Kensek
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 170-179
Technical Paper | doi.org/10.13182/NSE08-68
Transient Two-Dimensional Hydrodynamic Experiments
Aya Diab, Michael Corradini
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 180-199
Technical Paper | doi.org/10.13182/NSE08-18
Re-Analysis of Recent Neutron Diffusion and Transmission Measurements in Nuclear Graphite
C. R. Gould, A. I. Hawari, E. I. Sharapov
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 200-209
Technical Paper | doi.org/10.13182/NSE09-48
The Impact of Power Coastdown Operations on the Water Chemistry and Corrosion in Boiling Water Reactors
Tsung-Kuang Yeh, Mei-Ya Wang
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 210-223
Technical Paper | doi.org/10.13182/NSE09-27
Cross Sections for 239Pu(n,f) and 241Pu(n,f) in the Range En = 0.01 eV to 200 MeV
F. Tovesson, T. S. Hill
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 224-231
Technical Paper | doi.org/10.13182/NSE09-41
Recent Progress in the Design of a Tomographic Device for Measurements of the Three-Dimensional Pin-Power Distribution in Irradiated Nuclear Fuel Assemblies
Tobias Lundqvist Saleh, Staffan Jacobsson Svärd, Ane Håkansson, A. Bäcklin
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 232-239
Technical Note | doi.org/10.13182/NSE09-23TN
A Study of Photon Interaction and Photon Energy Absorption Effective Atomic Numbers for Some Amino Acids
Tejbir Singh, Updesh Kaur, Shivali Tandon, Parjit S. Singh
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 240-244
Technical Note | doi.org/10.13182/NSE09-35TN
Automated Design and Optimization of Pebble-Bed Reactor Cores
H. D. Gougar, A. M. Ougouag, W. K. Terry, K. N. Ivanov
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 245-269
Technical Paper | doi.org/10.13182/NSE08-89
Spatial Corrections for Pulsed-Neutron Reactivity Measurements
Yan Cao, John C. Lee
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 270-282
Technical Paper | doi.org/10.13182/NSE09-32
Exact Regional Monte Carlo Weight Cancellation for Second Eigenfunction Calculations
Thomas E. Booth, James E. Gubernatis
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 283-291
Technical Paper | doi.org/10.13182/NSE09-62
A Transport Acceleration Scheme for Multigroup Discrete Ordinates with Upscattering
Thomas M. Evans, Kevin T. Clarno, Jim E. Morel
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 292-304
Technical Paper | doi.org/10.13182/NSE09-28
Goal-Oriented h-Adaptivity for the Multigroup SPN Equations
Bruno Turcksin, Jean C. Ragusa, Wolfgang Bangerth
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 305-319
Technical Paper | doi.org/10.13182/NSE09-34
Extension of Differential Operator Method to Inhomogeneous Problems with Internal and External Neutron Sources
Kirill Fedorovich Raskach
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 320-330
Technical Paper | doi.org/10.13182/NSE09-47
The Newton-Krylov Method Applied to Negative-Flux Fixup in SN Transport Calculations
Erin D. Fichtl, James S. Warsa, Jeffery D. Densmore
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 331-341
Technical Paper | doi.org/10.13182/NSE09-51
