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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.
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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Latest News
Senate committee hears from energy secretary nominee Chris Wright
Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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Differential Neutron Production Cross Sections for 597-MeV Protons
W. B. Amian, R. C. Byrd, D. A. Clark, C. A. Goulding, M. M. Meier, G. L. Morgan, C. E. Moss
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE93-A35517
Shielding Measurements for 230-MeV Protons
J. V. Siebers, P. M. DeLuca, Jr., D. W. Pearson, G. Coutrakon
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 13-23
Technical Paper | doi.org/10.13182/NSE93-A35518
Measurement and Calculations of Angular Neutron Flux Spectra from Iron Slabs Bombarded with 14.8-MeV Neutrons
Yukio Oyama, Kazuaki Kosako, Hiroshi Maekawa
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 24-37
Technical Paper | doi.org/10.13182/NSE93-A35519
Observed Penetration of 14-MeV Neutrons in Various Materials
C. M. Logan, T. T. Komoto
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 38-42
Technical Paper | doi.org/10.13182/NSE93-A35520
Continuum Angular Distributions in the Transition Regions
C.Kalbach
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 43-49
Technical Paper | doi.org/10.13182/NSE93-A35521
Reactivity Feedback Mechanisms in Aqueous Fissile Solutions
Drew E. Kornreich
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 50-61
Technical Paper | doi.org/10.13182/NSE93-1
One-Dimensional Bimodal Model of Vibration and Impacting of Instrument Tubes in a Boiling Water Reactor
E. Laggiard, J. Runkel, D. Stegemann
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 62-70
Technical Paper | doi.org/10.13182/NSE93-A35523
Determination of the Excitation Function of the (n,xt) Process on Beryllium via Activation in Diverse Neutron Fields and Unfolding Code Calculations
R. Wölfle, A. Suhaimi, S. M. Qaim
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 71-75
Technical Notes | doi.org/10.13182/NSE93-A35524
A Measurement of the Effective Delayed Neutron Fraction of the Westinghouse Idaho Nuclear Company Slab Tank Assembly Using Rossi-α Techniques
Gregory D. Spriggs
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 76-80
Technical Notes | doi.org/10.13182/NSE93-A35525
Use of Padé Approximations in the Analytical Evaluation of the J(θ,β) Function and Its Temperature Derivative
R. S. Keshavamurthy, R. Harish
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 81-88
Technical Notes | doi.org/10.13182/NSE93-A35526
Scaling of Complex Phenomena in System Thermal Hydraulics
R. Bovalini, F. D’Auria, G. M. Galassi
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 89-111
Technical Paper | doi.org/10.13182/NSE93-A28521
Consistent Bn Theory for Slab Lattices
R. Roy, A. Hébert, G. Marleau
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 112-128
Technical Paper | doi.org/10.13182/NSE93-A28522
Development of a Third-Generation Superhomogénéisation Method for the Homogenization of a Pressurized Water Reactor Assembly
A. Hébert, G. Mathonnière
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 129-141
Technical Paper | doi.org/10.13182/NSE115-129
Application of H∞Control Theory to Power Control of a Nonlinear Reactor Model
Katsuo Suzuki, Junya Shimazaki, Yoshikuni Shinohara
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 142-151
Technical Paper | doi.org/10.13182/NSE92-112
Optimal Fuel Loading Pattern Design Using an Artificial Neural Network and a Fuzzy Rule-Based System
Han Gon Kim, Soon Heung Chang, Byung Ho Lee
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 152-163
Technical Paper | doi.org/10.13182/NSE93-A28525
Normalization and Minimum Values of the 239Pu Fission Cross Section
L. W. Weston, J. H. Todd, H.Derrien
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 164-172
Technical Paper | doi.org/10.13182/NSE93-A28526
Normalization of the 239Pu Fission Cross Section
C. Wagemans, P. Van Uffelen, A. Deruytter, R. Barthélémy, J. Van Gils
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 173-176
Technical Paper | doi.org/10.13182/NSE93-A28527
A Collision Probability Analysis of the Double-Heterogeneity Problem
A. Hébert
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 177-184
Technical Note | doi.org/10.13182/NSE115-177
An Experimental Investigation of the Effects of Surfactants on the Severity of Vapor Explosions
M. G. Kowal,M. F. Dowling, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 115 | Number 3 | November 1993 | Pages 185-192
Technical Paper | doi.org/10.13182/NSE93-A24048
Influence of Hydrides on Ductile Fracture in the Zr-2.5 Nb Alloy
S. A. Nikulin, M. A. Shtremel, V. G. Khanzhin, B. M. Fateev, V. A. Markelov
Nuclear Science and Engineering | Volume 115 | Number 3 | November 1993 | Pages 193-204
Technical Paper | doi.org/10.13182/NSE93-A24049
Influence of Burnable Gadolinia Poison on Coolant Void Reactivity in a Pressure-Tube-Type Heavy Water Reactor
Yasuki Kowata, Nobuo Fukumura
Nuclear Science and Engineering | Volume 115 | Number 3 | November 1993 | Pages 205-218
Technical Paper | doi.org/10.13182/NSE93-A24050
Numerical Divergence Effects of Equivalence Theory in the Nodal Expansion Method
M. R. Zika, T. J. Downar
Nuclear Science and Engineering | Volume 115 | Number 3 | November 1993 | Pages 219-232
Technical Paper | doi.org/10.13182/NSE93-A24051
Variational Nodal Transport Methods with Anisotropic Scattering
G. Palmiotti, C. B. Carrico, E. E. Lewis
Nuclear Science and Engineering | Volume 115 | Number 3 | November 1993 | Pages 233-243
Technical Paper | doi.org/10.13182/NSE92-110
Subspace Iteration for Nonsymmetric Eigenvalue Problems Applied to the λ-Eigenvalue Problem
Matthias G. Döring, Jens Chr. Kalkkuhl, Wolfram Schröder
Nuclear Science and Engineering | Volume 115 | Number 3 | November 1993 | Pages 244-252
Technical Paper | doi.org/10.13182/NSE93-A24053
A Two-Grid Acceleration Scheme for the Multigroup Sn Equations with Neutron Upscattering
B. T. Adams, J. E. Morel
Nuclear Science and Engineering | Volume 115 | Number 3 | November 1993 | Pages 253-264
Technical Paper | doi.org/10.13182/NSE115-253
Cell-Centered Imposed Diffusion Synthetic Acceleration for Weighted Difference Transport Methods
Y. Y. Azmy
Nuclear Science and Engineering | Volume 115 | Number 3 | November 1993 | Pages 265-272
Technical Note | doi.org/10.13182/NSE93-A24055
The Influence of Burnup-Dependent Fission Spectra on Reactor Pressure Vessel Irradiation
Frej Wasastjerna
Nuclear Science and Engineering | Volume 115 | Number 3 | November 1993 | Pages 273-278
Technical Note | doi.org/10.13182/NSE93-A24056
Spent-Fuel Assay Performance and Monte Carlo Analysis of the Rensselaer Slowing-Down-Time Spectrometer
Naeem M. Abdurrahman, Robert C. Block, Donald R. Harris, Rudolf E. Slovacek, Yong-Doek Lee, Francisco Rodriguez-Vera
Nuclear Science and Engineering | Volume 115 | Number 4 | December 1993 | Pages 279-296
Technical Paper | doi.org/10.13182/NSE92-94
Photoexcitation of 93mNb in the 5- to 30-MeV Gamma-Energy Range
J. Sáfár, L. Lakosi
Nuclear Science and Engineering | Volume 115 | Number 4 | December 1993 | Pages 297-299
Technical Paper | doi.org/10.13182/NSE93-A24059
Total Interaction Cross Sections of Several Sugars for 133Ba Photons
K. P. Gopinathan Nair, Channe Gowda, J. Shylaja Kumari, S. J. Anasuya, T. K. Umesh, Ramakrishna Gowda
Nuclear Science and Engineering | Volume 115 | Number 4 | December 1993 | Pages 300-303
Technical Paper | doi.org/10.13182/NSE93-A24060
Diffusion-Accelerated Solution of the Two-Dimensional Sn Equations with Bilinear-Discontinuous Differencing
J. E. Morel, J. E. Dendy, Jr., T. A. Wareing
Nuclear Science and Engineering | Volume 115 | Number 4 | December 1993 | Pages 304-319
Technical Paper | doi.org/10.13182/NSE93-A24061
Anisotropic Eigenvalue Spectrum Calculations of the Neutron Transport Operator with Low-Order Spatial Expansion Methods
P. Kohut
Nuclear Science and Engineering | Volume 115 | Number 4 | December 1993 | Pages 320-333
Technical Paper | doi.org/10.13182/NSE93-A24062
Depletion Perturbation Theory Within the Framework of an Advanced Hexagonal Nodal Method
T. J. Downar
Nuclear Science and Engineering | Volume 115 | Number 4 | December 1993 | Pages 334-340
Technical Note | doi.org/10.13182/NSE93-A24063
Analysis of Radially Heterogeneous ZPPR-13A Benchmark for Investigating the Spatial Dependence of the Calculated-to-Experimental Ratio for Control Rod Worths
B. Mahalakshmi, P. Mohanakrishnan
Nuclear Science and Engineering | Volume 115 | Number 4 | December 1993 | Pages 341-347
Technical Note | doi.org/10.13182/NSE93-A24064
