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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Recycling-Independent Core Design for the ENHS Fuel Self-Sustaining Reactor
Lanfranco Monti, Ki-Bog Lee, Massimiliano Fratoni, Marco Sumini, Ehud Greenspan
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 1-21
Technical Paper | doi.org/10.13182/NSE162-01
Application of hp Adaptivity to the Multigroup Diffusion Equations
Yaqi Wang, Jean Ragusa
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 22-48
Technical Paper | doi.org/10.13182/NSE161-22
An Analytical Approximation Solution for a Time-Dependent Neutron Transport Problem with External Source and Delayed Neutron Production
B. Merk
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 49-67
Technical Paper | doi.org/10.13182/NSE161-49
Reducing Parasitic Thermal Neutron Absorption in Graphite Reactors by 30%
C. D. Bowman, E. G. Bilpuch, D. C. Bowman, A. S. Crowell, C. R. Howell, K. McCabe, G. A. Smith, A. P. Tonchev, W. Tornow, V. Violet, R. B. Vogelaar, R. L. Walter, J. Yingling
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 68-77
Technical Paper | doi.org/10.13182/NSE161-68
Possible Configurations for the Thorium Molten Salt Reactor and Advantages of the Fast Nonmoderated Version
L. Mathieu, D. Heuer, E. Merle-Lucotte, R. Brissot, C. Le Brun, E. Liatard, J.-M. Loiseaux, O. MÃplan, A. Nuttin, D. Lecarpentier
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 78-89
Technical Paper | doi.org/10.13182/NSE07-49
Calculation and Evaluations for n + 54,56,57,58,natFe Reactions
Yinlu Han, Yue Zhang, Hairui Guo
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 90-110
Technical Paper | doi.org/10.13182/NSE161-90
The Fast Fission Factor Revisited
Lénárd Pál, Imre Pázsit
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 111-118
Technical Paper | doi.org/10.13182/NSE161-111
Neutrons from a Proton-Driven Deuterium Target as a Possible Competitor to Spallation for Nuclear Energy Applications
C. D. Bowman, D. C. Bowman, E. G. Bilpuch, A. S. Crowell, C. R. Howell, K. McCabe, G. A. Smith, A. P. Tonchev, W. Tornow, V. Vylet, R. L. Walter
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 119-124
Technical Note | doi.org/10.13182/NSE161-119
External Neutron Drive for Subcritical Reactors
D. C. Bowman, C. D. Bowman
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 125-129
Technical Note | doi.org/10.13182/NSE161-125
R-Matrix Analysis of 238U High-Resolution Neutron Transmissions and Capture Cross Sections in the Energy Range 0 to 20 keV
H. Derrien, A. Courcelle, L. C. Leal, N. M. Larson
Nuclear Science and Engineering | Volume 161 | Number 2 | February 2009 | Pages 131-159
Technical Paper | doi.org/10.13182/NSE161-131
Review of the CRAC and SILENE Criticality Accident Studies
Francis Barbry, Patrick Fouillaud, Pascal Grivot, Ludovic Reverdy
Nuclear Science and Engineering | Volume 161 | Number 2 | February 2009 | Pages 160-187
Technical Paper | doi.org/10.13182/NSE08-15
Fission Product Experimental Program: Validation and Computational Analysis
Nicolas Leclaire, Tatiana Ivanova, Eric Latang, Emmanuel Girault, Jean-François Thro
Nuclear Science and Engineering | Volume 161 | Number 2 | February 2009 | Pages 188-215
Technical Paper | doi.org/10.13182/NSE07-86
Coupled Space-Angle Adaptivity for Radiation Transport Calculations
HyeongKae Park, Cassiano R. E. de Oliveira
Nuclear Science and Engineering | Volume 161 | Number 2 | February 2009 | Pages 216-234
Technical Paper | doi.org/10.13182/NSE161-216
The Impact of Core Flow Rate on the Hydrogen Water Chemistry Efficiency in Boiling Water Reactors
Tsung-Kuang Yeh, Mei-Ya Wang
Nuclear Science and Engineering | Volume 161 | Number 2 | February 2009 | Pages 235-244
Technical Paper | doi.org/10.13182/NSE161-235
Shape Optimization of 19-Pin Wire-Wrapped Fuel Assembly of LMR Using Multiobjective Evolutionary Algorithm
Wasim Raza, Kwang-Yong Kim
Nuclear Science and Engineering | Volume 161 | Number 2 | February 2009 | Pages 245-254
Technical Note | doi.org/10.13182/NSE161-245
New Numerical Solution with the Method of Short Characteristics for 2-D Heterogeneous Cartesian Cells in the APOLLO2 Code: Numerical Analysis and Tests
Emiliano Masiello, Richard Sanchez, Igor Zmijarevic
Nuclear Science and Engineering | Volume 161 | Number 3 | March 2009 | Pages 257-278
Technical Paper | doi.org/10.13182/NSE161-257
A New Paradigm for Local-Global Coupling in Whole-Core Neutron Transport
E. E. Lewis, M. A. Smith, G. Palmiotti
Nuclear Science and Engineering | Volume 161 | Number 3 | March 2009 | Pages 279-288
Technical Paper | doi.org/10.13182/NSE161-279
Effect of 24195Am(n,) Reaction Branching Ratio on Fuel Cycle and Reactor Design Characteristics
Leonid Golyand, Eugene Shwageraus, Yigal Ronen
Nuclear Science and Engineering | Volume 161 | Number 3 | March 2009 | Pages 289-302
Technical Paper | doi.org/10.13182/NSE161-289
Hafnium Resonance Parameter Analysis Using Neutron Capture and Transmission Experiments
M. J. Trbovich, D. P. Barry, R. E. Slovacek, Y. Danon, R. C. Block, N. C. Francis, M. Lubert, J. A. Burke, N. J. Drindak, G. Leinweber, R. Ballad
Nuclear Science and Engineering | Volume 161 | Number 3 | March 2009 | Pages 303-320
Technical Paper | doi.org/10.13182/NSE161-303
Beryllium and Graphite High-Accuracy Total Cross-Section Measurements in the Energy Range from 24 to 900 keV
Y. Danon, R. C. Block, M. J. Rapp, F. J. Saglime, G. Leinweber, D. P. Barry, N. J. Drindak, J. G. Hoole
Nuclear Science and Engineering | Volume 161 | Number 3 | March 2009 | Pages 321-330
Technical Paper | doi.org/10.13182/NSE161-321
Theoretical Calculations and Analysis for the n + 59Co Reaction up to 20 MeV
Yue Zhang, Hairui Guo, Yinlu Han, Qingbiao Shen
Nuclear Science and Engineering | Volume 161 | Number 3 | March 2009 | Pages 331-345
Technical Paper | doi.org/10.13182/NSE161-331
Scaling Relations for Intermediate-Energy Proton-Nucleus Reactions with Small Energy Losses
R. J. Peterson
Nuclear Science and Engineering | Volume 161 | Number 3 | March 2009 | Pages 346-356
Technical Paper | doi.org/10.13182/NSE161-346
Subcritical Measurements of a Plutonium Sphere Reflected by Polyethylene and Acrylic
Jesson Hutchinson, Timothy Valentine
Nuclear Science and Engineering | Volume 161 | Number 3 | March 2009 | Pages 357-362
Technical Paper | doi.org/10.13182/NSE161-357
A Monte Carlo Approach to Nuclear Model Parameter Uncertainties Propagation
Cyrille De Saint Jean, Gilles Noguere, Benoit Habert, Bertrand Iooss
Nuclear Science and Engineering | Volume 161 | Number 3 | March 2009 | Pages 363-370
Technical Paper | doi.org/10.13182/NSE161-363
