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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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
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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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TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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Thermal Analysis of the Pennsylvania State University Breazeale Nuclear Reactor
J. A. Haag, S. H. Levine
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 6-15
Technical Paper | Reactor | doi.org/10.13182/NT73-A31313
Criticality Safety Evaluation of a Shipping Container for Moderated Low-Enriched Uranium Compounds
Ricardo Artigas
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 16-20
Technical Paper | Fuel Cycle | doi.org/10.13182/NT73-A31314
Thermal Considerations and Analysis for a Radioactive Waste Repository
R. D. Cheverton, W. D. Turner
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 21-33
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A31315
Compatibility of Refractory Metals with 244Cm2O3
J. R. DiStefano, K. H. Lin
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 34-45
Technical Paper | Material | doi.org/10.13182/NT73-A31316
Monitoring and Measurement of Carbon Activity in Sodium Systems
K. Natesan, T. F. Kassner
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 46-57
Technical Paper | Material | doi.org/10.13182/NT73-A31317
A Dual-Energy Method for Measuring Void Fractions in Flowing Mediums
F. E. LeVert, E. Helminski
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 58-60
Technical Note | Instrument | doi.org/10.13182/NT73-A31318
Temperature-Dependent k∞ for a ThO2-PuO2 HTGR Lattice
Darrell F. Newman
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 66-83
Technical Paper | Reactor | doi.org/10.13182/NT73-A31322
Models for the Safe Storage of Dry and Wet Fissile Oxides
C. L. Schuske, S. J. Altschuler
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 84-95
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A31323
Venting Device for Sodium-Cooled Fast Reactor Ceramic Fuel Elements
M. Martini, A. Gerosa
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 96-110
Technical Paper | Fuel | doi.org/10.13182/NT73-A31324
A Model for the Embrittlement and Annealing of Irradiated Steel
Paul J. De Meester
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 111-116
Technical Paper | Material | doi.org/10.13182/NT73-A31325
Improved Technology for Multiwatt Radioisotope Heater Units
A. W. Barsell, R. B. Goranson, P. R. Clements
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 117-125
Technical Paper | Aerospace | doi.org/10.13182/NT73-A31326
The Effect of Noncondensables on the Rate of Sodium Vapor Condensation from A Single-Rising HCDA Bubble
T. G. Theofanous, H. K. Fauske
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 132-139
Technical Paper | Reactor | doi.org/10.13182/NT73-A15874
Purification of Beryllium by Solvent Extraction from Carbonate Solutions with Quaternary Alkylammonium Carbonate
Forest G. Seeley, David J. Crouse
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 140-147
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A15875
Fatigue-Crack Propagation in Fast-Neutron-Irradiated Types-304 and -316 Stainless Steels
L. A. James, R. L. Knecht
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 148-155
Technical Paper | Material | doi.org/10.13182/NT73-A15876
Fuel Capsule Vent System Development for the Viking Radioisotope Thermoelectric Generator
Frederick A. Schumann
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 156-164
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A15877
Precession Damping of Solar Probes by Reradiative Forces
Philip T. Choong, Edward A. Mason
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 165-173
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A15878
FFTF Probe-Type Eddy-Current Flowmeter: Wet Versus dry Performance Evaluation in Sodium
T. J. Costello, R. L. Laubham, W. R. Miller, C. R. Smith
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 174-180
Technical Paper | Instruments | doi.org/10.13182/NT73-3
A Photoneutron Antimony-124-Beryllium System for Fissile Materials Assay
H. O. Menlove, R. A. Forster, D. L. Matthews
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 181-187
Technical Paper | Analysis | doi.org/10.13182/NT73-A15880
Track-Etch Radiography: Alpha, Proton, and Neutron
Harold Berger
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 188-198
Technical Paper | Analysis | doi.org/10.13182/NT73-A15881
Assay of Light Water Reactor Rods for Their Uranium-235 Content
K. Böhnel
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 199-201
Technical Paper | Analysis | doi.org/10.13182/NT73-A15882
Neutron Yield from a Small High Purity 238PuO2 Source
J. K. Bair, H. M. Butler
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 202-203
Technical Note | Radioisotope | doi.org/10.13182/NT73-A15883
An In-Reactor Temperature Monitor
G. L. Hofman
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 204-206
Technical Note | Instrument | doi.org/10.13182/NT73-A15884
