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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
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!
Latest Magazine Issues
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Will Palisades be the “comeback kid”?
Mike Mlynarek believes in this expression: “In the end it will be OK; and if it’s not OK, it’s not the end.”
As the site vice president at Palisades nuclear power plant in Covert Township, Mich., Mlynarek is overseeing one of the most exciting projects in the United States nuclear power industry. If all goes according to plan, Holtec’s Palisades plant will be splitting atoms once again by the end of 2025 and become the first U.S. nuclear facility to restart after being slated for decommissioning.
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HTC Experimental Program: Validation and Calculational Analysis
F. Fernex, T. Ivanova, F. Bernard, E. Latang, P. Fouillaud, J. F. Thro
Nuclear Science and Engineering | Volume 162 | Number 1 | May 2009 | Pages 1-24
Technical Paper | doi.org/10.13182/NSE07-52
Extensive Set of Cross-Section Covariance Estimates in the Fast Neutron Region
M. T. Pigni, M. Herman, P. Oblozinsky
Nuclear Science and Engineering | Volume 162 | Number 1 | May 2009 | Pages 25-40
Technical Paper | doi.org/10.13182/NSE162-25
Spatial Convergence Study of Discrete Ordinates Methods Via the Singular Characteristic Tracking Algorithm
J. I. Duo, Y. Y. Azmy
Nuclear Science and Engineering | Volume 162 | Number 1 | May 2009 | Pages 41-55
Technical Paper | doi.org/10.13182/NSE08-28
Development of the Subgroup Projection Method for Resonance Self-Shielding Calculations
Alain Hébert
Nuclear Science and Engineering | Volume 162 | Number 1 | May 2009 | Pages 56-75
Technical Paper | doi.org/10.13182/NSE162-56
Generalization of the SPRT Method for the Modeling of the Neutron Cross Sections in the Unresolved Resonance Range
E. Rich, Gilles Noguere, C. De Saint Jean, A. Tudora
Nuclear Science and Engineering | Volume 162 | Number 1 | May 2009 | Pages 76-86
Technical Paper | doi.org/10.13182/NSE162-76
Neutronic Analysis of an Advanced Fuel Design Concept for the High Flux Isotope Reactor
Ned Xoubi, R. T. Primm III, G. Ivan Maldonado
Nuclear Science and Engineering | Volume 162 | Number 1 | May 2009 | Pages 87-97
Technical Paper | doi.org/10.13182/NSE162-87
Real Variance Estimation Using an Intercycle Fission Source Correlation for Monte Carlo Eigenvalue Calculations
Hyung Jin Shim, Chang Hyo Kim
Nuclear Science and Engineering | Volume 162 | Number 1 | May 2009 | Pages 98-108
Technical Paper | doi.org/10.13182/NSE09-2
Inverse Generalized Perturbation Theory in Reactor Core Constrained Calculations
Aldo Dall'Osso
Nuclear Science and Engineering | Volume 162 | Number 1 | May 2009 | Pages 109-116
Technical Paper | doi.org/10.13182/NSE162-109
Feynman-Alpha and Rossi-Alpha Formulas with Delayed Neutrons for Subcritical Reactors Driven by Pulsed Non-Poisson Sources
Y. S. Rana, S. B. Degweker
Nuclear Science and Engineering | Volume 162 | Number 2 | June 2009 | Pages 117-133
Technical Papers | doi.org/10.13182/NSE08-13
Multiobjective Loading Pattern Optimization by Simulated Annealing Employing Discontinuous Penalty Function and Screening Technique
Tong Kyu Park, Han Gyu Joo, Chang Hyo Kim, Hyun Chul Lee
Nuclear Science and Engineering | Volume 162 | Number 2 | June 2009 | Pages 134-147
Technical Paper | doi.org/10.13182/NSE162-134
Nuclear Fuel Lattice Optimization Using Neural Networks and a Fuzzy Logic System
Juan José Ortiz, Alejandro Castillo, José Luis Montes, Raúl Perusquía, José Luis Hernández
Nuclear Science and Engineering | Volume 162 | Number 2 | June 2009 | Pages 148-157
Technical Paper | doi.org/10.13182/NSE162-148
An Improvement of the Monte Carlo Generalized Differential Operator Method by Taking into Account First- and Second-Order Perturbations of Fission Source
Kirill Fedorovich Raskach
Nuclear Science and Engineering | Volume 162 | Number 2 | June 2009 | Pages 158-166
Technical Paper | doi.org/10.13182/NSE162-158
Various Operating Regimes of a Subcritical System as a Function of Subcriticality in One-Group Theory
P. Saracco, G. Ricco
Nuclear Science and Engineering | Volume 162 | Number 2 | June 2009 | Pages 167-177
Technical Note | doi.org/10.13182/NSE162-167
Modeling of the n + 242Pu Reactions for Fast Reactor Applications
E. Rich, A. Tudora, G. Noguere, J. Tommasi, J.-F. Lebrat
Nuclear Science and Engineering | Volume 162 | Number 2 | June 2009 | Pages 178-191
Technical Note | doi.org/10.13182/NSE162-178
New Properties and Approximations of Doppler Broadening Functions Using Steffensen's Inequality
R. S. Keshavamurthy, R. S. Geetha
Nuclear Science and Engineering | Volume 162 | Number 2 | June 2009 | Pages 192-199
Technical Note | doi.org/10.13182/NSE162-192
Performance of an Automated Digital Gamma-Imaging System Based upon Cadmium Telluride-Complementary Metal-Oxide Semiconductor Sensor and Collimated 75Se Source for Nondestructive Testing
B. S. Kang, H. S. Cho, S. Y. Lee, S. I. Choi, J. E. Oh, H. M. Cho
Nuclear Science and Engineering | Volume 162 | Number 2 | June 2009 | Pages 200-207
Technical Note | doi.org/10.13182/NSE162-200
Evaluation of Self-Protection of 20% Uranium Denatured with 232U Against Unauthorized Reenrichment
E. F. Kryuchkov, V. A. Apse, V. A.Yufereva, V. B. Glebov, A. N. Shmelev
Nuclear Science and Engineering | Volume 162 | Number 2 | June 2009 | Pages 208-213
Technical Note | doi.org/10.13182/NSE162-208
Error Analysis of the Nodal Integral Method for Solving the Neutron Diffusion Equation in Two-Dimensional Cartesian Geometry
R. M. Ferrer, Y. Y. Azmy
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 215-233
Technical Paper | doi.org/10.13182/NSE162-215
Properties of the SN-Equivalent Integral Transport Operator in Slab Geometry and the Iterative Acceleration of Neutral Particle Transport Methods
Massimiliano Rosa, Yousry Y. Azmy, Jim E. Morel
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 234-252
Technical Paper | doi.org/10.13182/NSE162-234
Measurement of the Thermal Absorption Cross Section in Lucite Using Fermi Age Theory
Rene Sanchez, John Bounds, David Hayes, Travis Grove, Fredrik Tovesson
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 253-260
Technical Paper | doi.org/10.13182/NSE162-253
Steady-State Thermal-Hydraulic Analysis of the Oregon State University TRIGA Reactor Using RELAP5-3D
W. R. Marcum, B. G. Woods, M. R. Hartman, S. R. Reese, T. S. Palmer, S. T. Keller
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 261-274
Technical Paper | doi.org/10.13182/NSE08-63
Multiobjective Optimization of the Plate Element of Egyptian Research Reactor Using Genetic Algorithm
Mohamed El-Sayed Wahed, Wesam Zakaria Ibrahim, Ahmed Mostafa Effat
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 275-281
Technical Paper | doi.org/10.13182/NSE162-275
Analysis of Pebble-Fueled Zone Modeling Influence on High-Temperature Reactor Core Calculations
E. Bomboni, N. Cerullo, G. Lomonaco
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 282-298
Technical Note | doi.org/10.13182/NSE162-282
Some Notes on the Definition of Performance Parameters for Reactors and Fuel Cycles
W. F. G. van Rooijen
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 299-306
Technical Note | doi.org/10.13182/NSE162-299
Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors
Jan Dufek, J. Eduard Hoogenboom
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 307-311
Technical Note | doi.org/10.13182/NSE08-69TN
Absolute Total np and pp Cross-Section Determinations
R. A. Arndt, W. J. Briscoe, A. B. Laptev, I. I. Strakovsky, R. L. Workman
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 312-318
Technical Note | doi.org/10.13182/NSE162-312
