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Division Spotlight
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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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A Parametric Study of the DUPIC Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy
Daniel Rozon, Wei Shen
Nuclear Science and Engineering | Volume 138 | Number 1 | May 2001 | Pages 1-25
Technical Paper | doi.org/10.13182/NSE138-1-25
Split-Cell Exponential Characteristic Transport Method for Unstructured Tetrahedral Meshes
Charles R. Brennan, Rodney L. Miller, Kirk A. Mathews
Nuclear Science and Engineering | Volume 138 | Number 1 | May 2001 | Pages 26-44
Technical Paper | doi.org/10.13182/NSE01-A2200
Multidimensional Deterministic Nuclear Data Sensitivity and Uncertainty Code System: Method and Application
Ivan Kodeli
Nuclear Science and Engineering | Volume 138 | Number 1 | May 2001 | Pages 45-66
Technical Paper | doi.org/10.13182/NSE00-43
Boiling Water Reactor Loading Pattern Optimization Using Simple Linear Perturbation and Modified Tabu Search Methods
Suetsugu Jagawa, Takashi Yoshii, Akihiro Fukao
Nuclear Science and Engineering | Volume 138 | Number 1 | May 2001 | Pages 67-77
Technical Paper | doi.org/10.13182/NSE00-44
Transient Criticality in Fissile Solutions—Compressibility Effects
C. C. Pain, C. R. E. de Oliveira, A. J. H. Goddard, A. P. Umpleby
Nuclear Science and Engineering | Volume 138 | Number 1 | May 2001 | Pages 78-95
Technical Paper | doi.org/10.13182/NSE138-78
An Approximate Monte Carlo Adaptive Importance Sampling Method
Thomas E. Booth
Nuclear Science and Engineering | Volume 138 | Number 1 | May 2001 | Pages 96-103
Technical Paper | doi.org/10.13182/NSE01-A2204
High-Resolution Measurements and Calculations of Photon-Production Cross Sections for 16O(n,x) Reactions Induced by Neutrons with Energies Between 4 and 200 MeV
R. O. Nelson, M. B. Chadwick, A. Michaudon, P. G. Young
Nuclear Science and Engineering | Volume 138 | Number 2 | June 2001 | Pages 105-144
Technical Paper | doi.org/10.13182/NSE01-A2205
Measurement of the Thick-Target 9Be(p,n) Neutron Energy Spectra
W. B. Howard, S. M. Grimes, T. N. Massey, S. I. Al-Quraishi, D. K. Jacobs, C. E. Brient, J. C. Yanch
Nuclear Science and Engineering | Volume 138 | Number 2 | June 2001 | Pages 145-160
Technical Paper | doi.org/10.13182/NSE01-A2206
A Generic Model for the Resuspension of Multilayer Aerosol Deposits by Turbulent Flow
H. Friess, G. Yadigaroglu
Nuclear Science and Engineering | Volume 138 | Number 2 | June 2001 | Pages 161-176
Technical Paper | doi.org/10.13182/NSE01-A2207
Eigenvalue Sensitivity Theory for Resonance-Shielded Cross Sections
M. L. Williams, B. L. Broadhead, C. V. Parks
Nuclear Science and Engineering | Volume 138 | Number 2 | June 2001 | Pages 177-191
Technical Paper | doi.org/10.13182/NSE00-56
Unified Formulation of Nodal Expansion Method and Analytic Nodal Method Solutions to Two-Group Diffusion Equations
Hyun Chul Lee, Chang Hyo Kim
Nuclear Science and Engineering | Volume 138 | Number 2 | June 2001 | Pages 192-204
Technical Paper | doi.org/10.13182/NSE01-A2209
Inherent and Passive Safety Sodium-Cooled Fast Reactor Core Design with Minor Actinide and Fission Product Incineration
Hideaki Kuraishi, Tetsuo Sawada, Hisashi Ninokata, Hiroshi Endo
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 205-232
Technical Paper | doi.org/10.13182/NSE01-A2210
Improved Gamma-Heating Calculational Methods for Fast Reactors and Their Validation for Plutonium-Burning Configurations
Anton Lüthi, Rakesh Chawla, Gérald Rimpault
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 233-255
Technical Paper | doi.org/10.13182/NSE01-A2211
Discontinuous Finite Element SN Methods on Three-Dimensional Unstructured Grids
Todd A. Wareing, John M. McGhee, Jim E. Morel, Shawn D. Pautz
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 256-268
Technical Paper | doi.org/10.13182/NSE138-256
Fast Tree Multigrid Transport Application for the Simplified P3 Approximation
Petri Kotiluoto
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 269-278
Technical Paper | doi.org/10.13182/NSE01-A2213
Sensitivity Analysis of Nuclide Importance to One-Group Neutron Cross Sections
Hiroshi Sekimoto, Atsushi Nemoto, Yoshikane Yoshimura
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 279-294
Technical Paper | doi.org/10.13182/NSE01-A2214
Homogeneous 242mAm-Fueled Reactor for Neutron Capture Therapy
Y. Ronen, M. Aboudy, D. Regev
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 295-304
Technical Paper | doi.org/10.13182/NSE01-A2215
Design of a Receding Horizon Control System for Nuclear Reactor Power Distribution
Man Gyun Na
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 305-314
Technical Paper | doi.org/10.13182/NSE01-A2216
Importance of Delayed Neutrons on the Coupled Neutronic-Thermohydraulic Stability of a Natural Circulation Heavy Water-Moderated Boiling Light Water-Cooled Reactor
A. K. Nayak, M. Aritomi, V. Venkat Raj
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 315-321
Technical Note | doi.org/10.13182/NSE01-A2217
