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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
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February 2025
Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
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Evaluation and Propagation of the 239Pu Fission Cross-Section Uncertainties Using a Monte Carlo Technique
T. Kawano, K. M. Hanson, S. Frankle, P. Talou, M. B. Chadwick, R. C. Little
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE06-A2589
Neutron Transmission and Capture Measurements and Resonance Parameter Analysis of Neodymium from 1 to 500 eV
D. P. Barry, M. J. Trbovich, Y. Danon, R. C. Block, R. E. Slovacek, G. Leinweber, J. A. Burke, N. J. Drindak
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 8-25
Technical Paper | doi.org/10.13182/NSE06-A2590
Calculation of the Prompt Neutron Lifetime in the NBSR
Albert L. Hanson, Hans Ludewig, David J. Diamond
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 26-32
Technical Paper | doi.org/10.13182/NSE06-4
Photonuclear Physics in Radiation Transport - III: Actinide Cross Sections and Spectra
M.-L. Giacri-Mauborgne, D. Ridikas, M. B. Chadwick, P. G. Young, W. B. Wilson
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 33-40
Technical Paper | doi.org/10.13182/NSE06-A2592
Differential and Angle-Integrated Cross-Section Measurement for the 6Li(n,t)4He Reaction at En = 1.05, 1.54, and 2.25 MeV
Guohui Zhang, Rongtai Cao, Jinxiang Chen, Guoyou Tang, Yu. M. Gledenov, M. Sedysheva, G. Khuukhenkhuu
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 41-45
Technical Paper | doi.org/10.13182/NSE153-41
Collision Probabilities in r--z Geometry
R. D. M. Garcia
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 46-59
Technical Paper | doi.org/10.13182/NSE06-A2594
The Statistics of the Number of Neutron Collisions Prior to Absorption
Sara A. Pozzi, Imre Pázsit
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 60-68
Technical Paper | doi.org/10.13182/NSE06-A2595
Space-Time Correction for Reactivity Determination in Source-Driven Subcritical Systems
Viktoriya V. Kulik, John C. Lee
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 69-89
Technical Paper | doi.org/10.13182/NSE06-A2596
The Smallest Thermal Nuclear Reactor
Y. Ronen, E. Fridman, E. Shwageraus
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 90-92
Technical Paper | doi.org/10.13182/NSE06-A2597
MEND: A Program for Calculating the Complete Set of Nuclear Data of Medium-Heavy Nuclei in a Medium-Low Energy Region
Chong-Hai Cai
Nuclear Science and Engineering | Volume 153 | Number 1 | May 2006 | Pages 93-97
Computer Code Abstract | doi.org/10.13182/NSE05-06CCA
Probabilistic Techniques for Diagnosis of Multiple Component Degradations
Steven E. Aumeier, Bulent Alpay, John C. Lee, A. Ziya Akcasu
Nuclear Science and Engineering | Volume 153 | Number 2 | June 2006 | Pages 101-123
Technical Paper | doi.org/10.13182/NSE06-A2599
Estimation of Effective Parameters in a Lumped Nuclear Reactor Model Using Multiobjective Genetic Algorithms
Marzio Marseguerra, Enrico Zio, Raffaele Canetta
Nuclear Science and Engineering | Volume 153 | Number 2 | June 2006 | Pages 124-136
Technical Paper | doi.org/10.13182/NSE06-A2600
MCDET: A Probabilistic Dynamics Method Combining Monte Carlo Simulation with the Discrete Dynamic Event Tree Approach
Martina Kloos, Jörg Peschke
Nuclear Science and Engineering | Volume 153 | Number 2 | June 2006 | Pages 137-156
Technical Paper | doi.org/10.13182/NSE06-A2601
A Fuzzy Logic-Based Model for the Classification of Faults in the Pump Seals of the Primary Heat Transport System of a CANDU 6 Reactor
Marzio Marseguerra, Enrico Zio, Piero Baraldi, Irina Crenguta Popescu, Paul Ulmeanu
Nuclear Science and Engineering | Volume 153 | Number 2 | June 2006 | Pages 157-171
Technical Paper | doi.org/10.13182/NSE06-A2602
A Deep Burn Fuel Management Strategy for the Incineration of Military Plutonium in the Gas Turbine-Modular Helium Reactor Modeled in a Detailed Three-Dimensional Geometry by the Monte Carlo Continuous Energy Burnup Code
Alberto Talamo, Waclaw Gudowski
Nuclear Science and Engineering | Volume 153 | Number 2 | June 2006 | Pages 172-183
Technical Paper | doi.org/10.13182/NSE06-A2603
Time Series Analysis of Monte Carlo Fission Sources—II: Confidence Interval Estimation
Taro Ueki, Brian R. Nease
Nuclear Science and Engineering | Volume 153 | Number 2 | June 2006 | Pages 184-191
Technical Paper | doi.org/10.13182/NSE05-15
Calculations of Proton-Induced Neutron Production Cross Sections on 232Th up to 1.6 GeV
B. Sarer, M. Günay, A. Aydin, E. Tel, A. Arasoglu
Nuclear Science and Engineering | Volume 153 | Number 2 | June 2006 | Pages 192-199
Technical Note | doi.org/10.13182/NSE06-A2605
Electronic Structure of High Oxidation State Actinide Species: Theoretical and Experimental Approaches
Sandrine Hilaire, Dominique Guillaumont, Fabien Gutierez, Christophe Denauwer, Franck Wastin, Eric Colineau, Thomas Gouder, Jean Rebizant, Jean-Claude Berthet, Daniel Meyer, Eric Simoni
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 203-206
Technical Paper | doi.org/10.13182/NSE06-A2606
Modeling Selectivity in Liquid/Liquid Extraction
D. Guillaumont, Ph. Guilbaud, C. Sorel, F. Gutierrez, S. Chalmet, M. Defranceschi
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 207-222
Technical Paper | doi.org/10.13182/NSE06-A2607
Complexation of Lanthanide(III) and Actinide(III) Cations with Tridentate Nitrogen-Donor Ligands: A Luminescence and Spectrophotometric Study
M. Miguirditchian, D. Guillaneux, N. François, S. Airvault, S. Ducros, D. Thauvin, C. Madic, M. Illemassène, G. Lagarde, J.-C. Krupa
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 223-232
Technical Paper | doi.org/10.13182/NSE06-A2608
FUJI: A Comparative Irradiation Test with Pellet, Sphere-Pac, and Vipac Fuels
Ch. Hellwig, K. Bakker, T. Ozawa, M. Nakamura, F. Ingold, L. Å. Nordström, Y. Kihara
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 233-244
Technical Paper | doi.org/10.13182/NSE06-A2609
Oxide and Nitride TRU Fuels: Lessons Drawn from the CONFIRM and FUTURE Projects of the 5th European Framework Program
Sylvie Pillon, J. Wallenius
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 245-252
Technical Paper | doi.org/10.13182/NSE06-A2610
Promising Pyrochemical Actinide/Lanthanide Separation Processes Using Aluminum
Olivier Conocar, Nicolas Douyere, Jean-Paul Glatz, Jérôme Lacquement, Rikard Malmbeck, Jérôme Serp
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 253-261
Technical Paper | doi.org/10.13182/NSE06-A2611
Zirconolite for Minor Actinide Containment and Alpha Irradiation Resistance
F. Jorion, X. Deschanels, T. Advocat, F. Desmouliere, J. N. Cachia, S. Peuget, D. Roudil, G. Leturcq
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 262-271
Technical Paper | doi.org/10.13182/NSE06-A2612
Development and Characterization of Rare Earth-Rich Glassy Matrices Envisaged for the Immobilization of Concentrated Nuclear Waste Solutions
I. Bardez, D. Caurant, J. L. Dussossoy, P. Loiseau, C. Gervais, F. Ribot, D. R. Neuville, N. Baffier, C. Fillet
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 272-284
Technical Paper | doi.org/10.13182/NSE06-A2613
Contribution of Monte Carlo Modeling to Understanding the Alteration of Nuclear Glasses by Water
Aurélien Ledieu, François Devreux, Philippe Barboux, Yves Minet
Nuclear Science and Engineering | Volume 153 | Number 3 | July 2006 | Pages 285-300
Technical Paper | doi.org/10.13182/NSE06-A2614
