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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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Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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Critical Experiments with Homogeneous PuO2-Polystyrene at 50 H/Pu
S. R. Bierman, E. D. Clayton
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 5-13
Technical Paper | Reactor | doi.org/10.13182/NT72-A31157
The Potential of a Laser-Induced Fusion Device as a Thermal-Neutron Source
R. M. Brugger
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 14-24
Technical Paper | Reactor | doi.org/10.13182/NT72-A31158
Single- and Two-Phase Pressure Drops on a 6 × 6 Rod Bundle at 70 atm
P. Grillo, G. Mazzone
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 25-35
Technical Paper | Reactor | doi.org/10.13182/NT72-A31159
Waste Disposal Systems for Closed Cycle Water Reactors
Charles T. Chave
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 36-48
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31160
Review of the Low Energy Scattering Cross Sections of Deuterium
B. R. Leonard, Jr.
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 49-55
Technical Paper | Material | doi.org/10.13182/NT72-A31161
Developments in Use of Californium-252 for Neutron Radiography
John P. Barton
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 56-67
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31162
A New Model for Estimating Space Proton Dose to Body Organs
R. W. Langley, M. P. Billings
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 68-74
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31163
Explosive Excavation Research: Projects TUGBOAT and TRINIDAD
Robert L. LaFrenz, Walter C. Day
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 75-84
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT72-A31164
Chimney Gas Radiochemistry in Nuclear Gas Stimulation Applications
C. F. Smith
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 85-92
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT72-A31165
Advantages of Primary System Flow Control During Reactor Scram in an LMFBR
William J. Metevia, Jon C. Gilbertson
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 93-98
Technical Note | Reactor | doi.org/10.13182/NT72-A31166
Kinetic Parameters in a Plutonium Lattice Containing Water Regions
V. O. Uotinen, W. P. Stinson, S. P. Singh
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 109-113
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31141
Plutonium and Fission Product Redistribution in Mixed-Oxide Fuels During Irradiation
J. K. Bahl, M. D. Freshley
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 114-124
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31142
Mixed-Oxide Fuel Irradiations in the Plutonium Recycle Test Reactor
M. D. Freshley
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 125-176
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31143
The Transient Behavior of Vipac and Pellet Thermal Reactor Oxide Fuels
M. D. Freshley, L. J. Harrison
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 177-191
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31144
Measurement of k∞ and Relative Reaction Rates in an H2O-Moderated UO2-PuO2 Particulate Fueled Lattice
Darrell F. Newman
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 192-208
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31145
The Defect Performance of UO2-PuO2 Thermal Reactor Fuel
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 209-228
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31146
The Determination of Ratios of Effective Cross Sections from Burnup Data from the Saxton Plutonium Program
P. E. Coudron, R. P. Matsen, L. C. Schmid
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 229-238
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31147
Behavior of Discrete Plutonium-Dioxide Particles in Mixed-Oxide Fuel During Rapid Power Transients
M. D. Freshley, E. A. Aitken, D. C. Wadekamper, R. L. Johnson, W. G. Lussie
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 239-248
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31148
Radiation Dose Rates from UO2-PuO2 Thermal Reactor Fuels
L. G. Faust, L. W. Brackenbush, R. C. Smith, L. L. Nichols, D. W. Brite
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 249-256
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31149
Lattices of Plutonium-Enriched Rods in Light Water—Part I: Experimental Results
V. O. Uotinen, J. H. Lauby, L. C. Schmid, W. P. Stinson
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 257-271
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31150
Lattices of Plutonium-Enriched Rods in Light Water—Part II: Theoretical Analysis of Plutonium-Fueled Systems
R. C. Liikala, V. O. Uotinen, U. P. Jenquin
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 272-296
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31151
Spectrum-Averaged Cross Sections Deduced from Burnup Data and Their Application to Methods Verification
L. C. Schmid, D. E. Christensen, B. H. Duane, R. C. Liikala, R. P. Matsen
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 297-318
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31152
Burnup and Power Shift Effects in Large Fast Breeder Reactors
J. S. Philbin, R. A. Axford
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 327-342
Technical Paper | Reactor | doi.org/10.13182/NT72-A16031
The Determination of Ratios of Effective Cross Sections from Measured Burnup Data for Yankee Rowe
R. P. Matsen
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 343-358
Technical Paper | Reactor | doi.org/10.13182/NT72-A16032
Space-Energy-Dependent Physics Problems of Plutonium Fuels in HTGRs
Keith E. Asmussen, Paul Wälti
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 359-365
Technical Paper | Reactor | doi.org/10.13182/NT72-A16033
Vapor Transport Limits of Liquid Metal Heat Pipes
Don W. DeMichele, Monte V. Davis
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 366-383
Technical Paper | Reactor | doi.org/10.13182/NT72-A16034
Evaluation of Absorber Materials Performance in Hfir Control Cylinders
R. W. Knight, A. E. Richt
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 384-390
Technical Paper | Reactor | doi.org/10.13182/NT72-A16035
The Containment of Fission Product Iodine in the Reprocessing of Lmfbr Fuels by Pyrochemical Reactions
M. Krumpelt, J. J. Heiberger, V. A. Maroni, M. J. Steindler
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 391-395
Technical Paper | Chemical Processing | doi.org/10.13182/NT72-A16036
Neutron Radiation Characteristics of Plutonium Dioxide Fuel
Mojtaba Taherzadeh, Peter J. Gingo
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 396-410
Technical Paper | Fuel | doi.org/10.13182/NT72-A16037
Correlation of Irradiation Data Using Activation Fluences and Irradiation Temperature
John H. Lynch
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 411-421
Technical Paper | Fuel | doi.org/10.13182/NT72-A16038
Subcritical Multiplication of Californium-252 Neutrons and ITS Applications
L. E. Hansen, N. A. Wogman, R. W. Perkins, E. D. Clayton
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 422-430
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A16039
Prediction of Underground Nuclear Explosion Effects in Wagon Wheel Sandstone
Robert W. Terhune
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 431-446
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT72-A16040
Nerva Flight Engine Control System Design
H. H. Norman, E. A. Parziale, J. K. Saluja, R. F. Schenz, Jr.
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 447-454
Nuclear Technology | Aerospace | doi.org/10.13182/NT72-A16041
Nondestructive Assay of Power Reactor Fuel Assemblies
C. R. Weisbin, R. H. Augustson, J. S. Hendricks, A. E. Evans, G. D. Turner, K. D. Böhnel
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 455-461
Technical Paper | Analysis | doi.org/10.13182/NT72-A16042
On-line Reactivity Feedback Analysis of Ebr-II by Rod Drop
H. A. Larson, I. A. Engen
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 462-464
Technical Note | Reactor | doi.org/10.13182/NT72-A16043
Cross Flow Resistance in Rod Bundle Cores
Joel Weisman
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 465-469
Technical Note | Reactor | doi.org/10.13182/NT72-A16044
Breeding Ratio, Inventory, and Doubling time in A D-T Fusion Reactor
W. F. Vogelsang
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 470-474
Technical Note | Reactor | doi.org/10.13182/NT72-A16045
