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Division Spotlight
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.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
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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
