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X-energy raises $700M in latest funding round
Advanced reactor developer X-energy has announced that it has closed an oversubscribed Series D financing round of approximately $700 million. The funding proceeds are expected to be used to help continue the expansion of its supply chain and the commercial pipeline for its Xe-100 advanced small modular reactor and TRISO-X fuel, according the company.
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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