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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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As demand for artificial intelligence and data centers grows, President Biden issued an executive order yesterday aimed to ensure clean-energy power supply for the technology.
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The Ribon Extended Self-Shielding Model
Alain Hébert
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 1-24
Technical Paper | doi.org/10.13182/NSE151-1-24
Plutonium Multirecycling in Standard PWRs Loaded with Evolutionary Fuels
Gilles Youinou, Alfredo Vasile
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 25-45
Technical Paper | doi.org/10.13182/NSE05-A2526
Iterative Two- and One-Dimensional Methods for Three-Dimensional Neutron Diffusion Calculations
Hyun Chul Lee, Deokjung Lee, Thomas J. Downar
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 46-54
Technical Paper | doi.org/10.13182/NSE04-68
Deterministic Local Sensitivity Analysis of Augmented Systems - I: Theory
Dan G. Cacuci, Mihaela Ionescu-Bujor
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 55-66
Technical Paper | doi.org/10.13182/NSE05-A2528
Deterministic Local Sensitivity Analysis of Augmented Systems—II: Applications to the QUENCH-04 Experiment Using the RELAP5/MOD3.2 Code System
Mihaela Ionescu-Bujor, Xuezhou Jin, Dan G. Cacuci
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 67-81
Technical Paper | doi.org/10.13182/NSE151-67
Development of the CRISP Package for Spallation Studies and Accelerator-Driven Systems
S. Anefalos, A. Deppman, Gilson da Silva, J. R. Maiorino, A. dos Santos, F. Garcia
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 82-87
Technical Paper | doi.org/10.13182/NSE05-A2530
Refueling Simulation Strategy of a CANDU Reactor Based on Optimum Zone Controller Water Levels
Hangbok Choi, Do Heon Kim
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 88-94
Technical Paper | doi.org/10.13182/NSE05-A2531
In-Phase and Out-of-Phase Oscillations in BWRs: Impact of Azimuthal Asymmetry and Second Pair of Eigenvalues
Quan Zhou, Rizwan-uddin
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 95-113
Technical Paper | doi.org/10.13182/NSE05-A2532
Approach to Assessing the Potential Effects of Colloidal Radionuclide Transport on Nuclear Waste Repository Performance
David A. Pickett, William L. Dam
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 114-120
Technical Paper | doi.org/10.13182/NSE05-A2533
Comparison of Oxidation Behaviors of Different Grades of Nuclear Graphite
Xiaowei Luo, Jean-Charles Robin, Suyuan Yu
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 121-127
Technical Paper | doi.org/10.13182/NSE05-A2534
Interaction Between Hyperalkaline Fluids and Rocks Hosting Repositories for Radioactive Waste: Reactive Transport Simulations
Josep M. Soler, Urs K. Mäder
Nuclear Science and Engineering | Volume 151 | Number 1 | September 2005 | Pages 128-133
Technical Note | doi.org/10.13182/NSE05-A2535
Reich-Moore Parameterization of (,n) Reactions on Light Nuclei: Impact on a Neutron Source Calculation in an Oxide Fuel
Richard Babut, Olivier Bouland, Eric Fort
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 135-156
Technical Paper | doi.org/10.13182/NSE05-A2536
An Sn Spatial Discretization Scheme for Tetrahedral Meshes
Jim E. Morel, James S. Warsa
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 157-166
Technical Paper | doi.org/10.13182/NSE05-A2537
Spherical Harmonics Finite Element Transport Equation Solution Using a Least-Squares Approach
E. Varin, G. Samba
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 167-183
Technical Paper | doi.org/10.13182/NSE05-A2538
Multiple Timescale Expansions for Neutron Kinetics - I: Illustrative Application to the Point-Kinetics Model
B. R. Merk, D. G. Cacuci
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 184-193
Technical Paper | doi.org/10.13182/NSE05-A2539
Multiple Timescale Expansions for Neutron Kinetics - II: Illustrative Application to P1 and P3 Equations
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 194-211
Technical Paper | doi.org/10.13182/NSE05-A2540
Temporal Adaptive Three-Grid Correction Method for Transient Nonlinear Nodal Calculations
Ku Young Chung, Chang Hyo Kim
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 212-223
Technical Paper | doi.org/10.13182/NSE05-A2541
Insights into Stratified Splitting Techniques for Monte Carlo Neutron Transport
Thomas E. Booth
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 224-236
Technical Paper | doi.org/10.13182/NSE05-A2542
The Inversion Point of the Isothermal Reactivity Coefficient of the IPEN/MB-01 Reactor - II: Theoretical Analysis
A. dos Santos, G. S. de Andrade e Silva, A. G. Mendonça, R. Fuga, A. Y. Abe
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 237-250
Technical Paper | doi.org/10.13182/NSE05-A2543
Benchmark Experiments of Thermal Neutron and Capture Gamma-Ray Distributions in Concrete Using 252Cf
Yoshihiro Asano, Takeshi Sugita, Hideyuki Hirose, Takenori Suzaki
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 251-259
Technical Paper | doi.org/10.13182/NSE05-A2544
Impact of High Burnup on PWR Spent Fuel Characteristics
Zhiwen Xu, Mujid S. Kazimi, Michael J. Driscoll
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 261-273
Technical Paper | doi.org/10.13182/NSE05-A2545
Generalized Coarse-Mesh Rebalance Method for Acceleration of Neutron Transport Calculations
Akio Yamamoto
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 274-282
Technical Paper | doi.org/10.13182/NSE151-274
Information Theory and Undersampling Diagnostics for Monte Carlo Simulation of Nuclear Criticality
Taro Ueki
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 283-292
Technical Paper | doi.org/10.13182/NSE05-A2547
Neutron Production in Semiprototypic Target Assemblies for Accelerator Transmutation Technology
G. L. Morgan, K. R. Alrick, D. W. Bowman, F. C. Cverna, N. S. P. King, P. E. Littleton, G. A. Greene, A. L. Hanson, C. L. Snead, Jr., J. M. Hall, J. Frehaut, X. Ledoux, S. Leray, E. Petibon, R. T. Thompson, P. D. Ferguson, E. A. Henry, T. E. Ward
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 293-304
Technical Paper | doi.org/10.13182/NSE05-A2548
The Stability of 9Cr-ODS Oxide Particles Under Heavy-Ion Irradiation
T. R. Allen, J. Gan, J. I. Cole, S. Ukai, S. Shutthanandan, S. Thevuthasan
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 305-312
Technical Paper | doi.org/10.13182/NSE05-A2549
Steam Generator Two-Phase-Flow Numerical Simulation with Liquid and Gas Momentum Equations
M. Grandotto, P. Obry
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 313-318
Technical Paper | doi.org/10.13182/NSE05-A2550
Total and Capture Cross Sections of Dysprosium Isotopes up to 20 MeV
Y. D. Lee, S. Y. Oh, J. H. Chang
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 319-334
Technical Note | doi.org/10.13182/NSE05-A2551
Core Subcriticality as a Tool of Safety Enhancement
Pavel M. Bokov, Danas Ridikas, Igor Slessarev, Oliver Köberl
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 335-343
Technical Note | doi.org/10.13182/NSE05-A2552
Reactivity Effects of Streaming Between Discrete Boron Carbide Particles in Neutron Absorber Panels for Storage or Transport of Spent Nuclear Fuel
Stanley E. Turner
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 344-347
Technical Note | doi.org/10.13182/NSE05-A2553
High-Resolution Room Temperature Spectroscopy with Lanthanum Halides
Sanjoy Mukhopadhyay
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 348-354
Technical Note | doi.org/10.13182/NSE05-A2554
Oxidation Kinetics of Spent Low-Level Radioactive Resins
Y.-J. Huang, H. Paul Wang, Chih C. Chao, H. H. Liu, M. C. Hsiao, S. H. Liu
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 355-360
Technical Note | doi.org/10.13182/NSE05-A2555
CEARPGA II: A Monte Carlo Simulation Code for Prompt-Gamma-Ray Neutron Activation Analysis
Wenchao Zhang, Robin P. Gardner
Nuclear Science and Engineering | Volume 151 | Number 3 | November 2005 | Pages 361-373
Computer Code Abstract | doi.org/10.13182/NSE05-A2556
