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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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Liquid Metal Breeder Reactor (LIMB) Nuclear Evaluation
Robert J. Teitel, John B. Brown
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 13-24
Technical Paper | doi.org/10.13182/NT65-A20459
Experience with High Pressure Heavy-Water Systems at NPD
A. C. Hoyle, G. R. Howey
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 25-32
Technical Paper | doi.org/10.13182/NT65-A20460
Excursion-Limiting Fuse for the Mixed Spectrum Critical Assembly
K. Hikido, G. V. Brynsvold, H. F. Johnston
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 33-38
Technical Paper | doi.org/10.13182/NT65-A20461
Effects of 1.0% Superimposed Mean Strain on the Bending Fatigue Strength of Zircaloy-4
D. F. Mowbray
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 39-48
Technical Paper | doi.org/10.13182/NT65-A20462
Analysis of a Radioisotope Thrustor-Auxiliary Power Unit
David F. Berganni, Robert R. Barthelemy
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 49-54
Technical Paper | doi.org/10.13182/NT65-A20463
Fast Reactor Fuel Burnup
F. R. Channon, J. D. Luoma, E. D. Frankhouser
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 55-61
Technical Paper | doi.org/10.13182/NT65-A20464
Void-Fraction Measurements in Cavitating Mercury
Frederick G. Hammitt, Willy Smith, Ian E. B. Lauchlan, Richard D. Ivany, M. John Robinson
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 62-68
Technical Paper | doi.org/10.13182/NT65-A20465
Out-of-Pile Steam-Fraction Determination by Neutron-Beam Attenuation
William T. Sha, Charles F. Bonilla
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 69-75
Technical Paper | doi.org/10.13182/NT65-A20466
The Education, Experience, Training, and Certification of Reactor Operators at AEC-Owned Reactors
Walter S. Wilgus, Whittie J. McCool
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 76-81
Technical Paper | doi.org/10.13182/NT65-A20467
The Settled-Bed Fast-Reactor Concept—1 000-MWe Reactor Design
L. Green, M. M. Levine, A. Aronson, W. Bent, D. A. Goellner, J. J. McNicholas, G. Nugent, G. Pancer, H. Susskind, J. Chernick, D. Gurinsky, L. P. Hatch
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 107-130
Technical Paper | doi.org/10.13182/NT65-A20478
Fuel Management for an Intermediate Power Research Reactor
Ernest E. Hill
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 131-135
Technical Paper | doi.org/10.13182/NT65-A20479
Production of the Heaviest Elements by Multiple Neutron Capture
J. Milsted, P. R. Fields, D. N. Metta
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 136-144
Technical Paper | doi.org/10.13182/NT65-A20480
The Radioisotope-Powered Bimetallic-Disk Engine
Calvin C. Silverstein
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 145-150
Technical Paper | doi.org/10.13182/NT65-A20481
Reactor Production of 109 Cd: Isotopic Composition and Use as an X-Ray Source
Howard T. Russell
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 151-154
Technical Paper | doi.org/10.13182/NT65-A20482
Electrodeposition of 99Tc Metal
Technetium metal can be electrodeposited almost quantitatively from dilute solutions of pertechnetate ion in acidic ammonium oxalate. Films up to 18 mg/cm2 have been deposited as dense adherent coatings on copper, gold, silver and platinum at a current density of 1.3 amp/cm2.
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 155-157
Technical Paper | doi.org/10.13182/NT65-A20483
Vacuum Distillation of Magnesium Metal
W. D. Box
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 158-159
Technical Paper | doi.org/10.13182/NT65-A20484
Effect of Elevated-Temperature Irradiation on Hastelloy N
W. R. Martin, J. R. Weir
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 160-167
Technical Paper | doi.org/10.13182/NT65-A20485
Behavior of Uranium Sulfide Fast-Reactor-Type Fuel Specimens Under Transient Heating in Treat
L. E. Robinson, C. E. Dickerman, R. Carlander, C. August, C. Mueller
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 168-175
Technical Paper | doi.org/10.13182/NT65-A20486
Radiation Exposures in Fabricating 233U-Th Fuels
J. P. Nichols, R. E. Brooksbank, D. E. Ferguson
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 176-178
Technical Paper | doi.org/10.13182/NT65-A20487
Determination of Zirconium by Activation and Chemical Separation of 97Nb
T. K. Choy, H. R. Lukens, G. H. Andersen
Nuclear Technology | Volume 1 | Number 2 | April 1965 | Pages 179-183
Technical Paper | doi.org/10.13182/NT65-A20488
N S Savannah Containment Integrity, Its Measurement and Improvement
James H. Taylor
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 213-218
Technical Paper | doi.org/10.13182/NT65-A20504
Head-end Dissolution for UC Processes and UC-PuC Reactor Fuels
J. R. Flanary, J. H. Goode, M. J. Bradley, L. M. Ferris, J. W. Ullmann, G. C. Wall
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 219-224
Technical Paper | doi.org/10.13182/NT65-A20505
The Evaluation and Measurement of Reactor-Safety Performance
H. J. Larson, K. Stratton
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 225-229
Technical Paper | doi.org/10.13182/NT65-A20506
Fabrication of Radioactive Samples for Cross-Section Measurements
J. R. Berreth
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 230-234
Technical Paper | doi.org/10.13182/NT65-A20507
General Corrosion of Incoloy-800® in Simulated Superheat Reactor Environment
W. L. Pearl, E. G. Brush, G. G. Gaul, G. P. Wozadlo
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 235-245
Technical Paper | doi.org/10.13182/NT65-A20508
Corrosion-Rate-Law Considerations in Superheated Steam
E. G. Brush
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 246-251
Technical Paper | doi.org/10.13182/NT65-A20509
The Failure of Stressed Zircaloy in Aqueous Chloride Solutions
K. C. Thomas, R. J. Allio
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 252-258
Technical Paper | doi.org/10.13182/NT65-A20510
Technique for Optimizing the Composition of Regenerating-Neutron-Flux Monitors
W. L. Bunch
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 259-266
Technical Paper | doi.org/10.13182/NT65-A20511
Continuous On-reactor Measurement of Instantaneous Corrosion Rates
R. B. Richman
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 267-270
Technical Paper | doi.org/10.13182/NT65-A20512
Engineering Development of a Fluid-bed Fluoride Volatility Process I Bench-Scale Studies
D. Ramaswami, N. M. Levitz, A. A. Jonke
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 293-300
Technical Paper | doi.org/10.13182/NT65-A20525
Engineering Development of a Fluid-bed Fluoride Volatility Process II Pilot-Scale Studies
John T. Holmes, Howard Stethers, John J. Barghusen
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 301-309
Technical Paper | doi.org/10.13182/NT65-A20526
Hydrogen Reduction of Pu(IV) to Pu(III)
Robert H. Rainey
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 310-311
Technical Paper | doi.org/10.13182/NT65-A20527
Neutron and Gamma-Ray Die-Away in a Heterogenous System
W. R. Mills, Jr., L. S. Allen, F. Selig, R. L. Caldwell
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 312-321
Technical Paper | doi.org/10.13182/NT65-A20528
Design and Economic Study of a Gas-phase Chemonuclear Ozone Process
M. Beller, D. Goellner, M. Steinberg
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 322-326
Technical Paper | doi.org/10.13182/NT65-A20529
244Cm Production and Separation—Status of the Pilot Production Program at Savannah River
Harold J. Groh, Richard T. Huntoon, Carl S. Schlea, James A. Smith, Fred H. Springer
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 327-336
Technical Paper | doi.org/10.13182/NT65-A20530
Displacement Spike Effects in Copper-rich Copper-Iron Alloys
A. Boltax
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 337-347
Technical Paper | doi.org/10.13182/NT65-A20531
Preparation of PuC Pellets by Vacuum Sintering
O. L. Kruger
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 348-355
Technical Paper | doi.org/10.13182/NT65-A20532
A Three-Decade Exponential Current Generator for Testing Reactor Period Meters
James H. Talboy
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 356-358
Technical Paper | doi.org/10.13182/NT65-A20533
A Comparison of Shielding Calculations with Absolute Measurements in Massive Shields
Erkki J. Aalto
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 359-374
Technical Paper | doi.org/10.13182/NT65-A20534
Microdetermination of Ruthenium in Uranium Compounds
O. A. Vita, C. F. Trivisonno
Nuclear Technology | Volume 1 | Number 4 | August 1965 | Pages 375-380
Technical Paper | doi.org/10.13182/NT65-A20535
Ordered Packed-Bed Fuel Elements
H. Susskind, W. E. Winsche, W. Becker
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 405-411
Technical Paper | doi.org/10.13182/NT65-A20549
Papers from the Symposium on Behavior of Stainless Steel in Reactors American Nuclear Society Winter Meeting San Francisco, December, 1964
W. L. Pearl
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Page 412
Technical Paper | doi.org/10.13182/NT65-A20550
Stainless-Steel-Clad Fuel Rod Failures
R. N. Duncan, W. H. Arlt, H. E. Williamson, C. J. Baroch, J. P. Hoffmann, T. J. Pashos
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 413-418
Technical Paper | doi.org/10.13182/NT65-A20551
Evaluation of Highly Irradiated Yankee Fuel Cladding
W. R. Smalley
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 419-424
Technical Paper | doi.org/10.13182/NT65-A20552
Performance of Thin-Walled Stainless-Steel-Clad Fuel Rods
D. R. McClintock, E. Paxson, H. M. Ferrari
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 425-431
Technical Paper | doi.org/10.13182/NT65-A20553
Boron Stainless-Steel Fuel-Element Cladding in the Indian Point Reactor
C. R. Johnson
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 432-438
Technical Paper | doi.org/10.13182/NT65-A20554
Fatigue and Burst Tests on Irradiated In-Pile Stainless-Steel Pressure Tubes
L. A. Waldman, M. Doumas
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 439-445
Technical Paper | doi.org/10.13182/NT65-A20555
Corrosion Product Behavior in Stainless-Steel-Clad Water Reactor Systems
G. Russell Taylor, Paul Cohen
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 446-452
Technical Paper | doi.org/10.13182/NT65-A20556
Development of Test to Simulate Intergranular Cracking of Nonsensitized Stainless Steel in Water Reactor Environments
A. E. Pickett, W. L. Pearl, M. C. Rowland
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 453-461
Technical Paper | doi.org/10.13182/NT65-A20557
Radiation Effects on the Mechanical Properties and Microstructure of Type-304 Stainless Steel
J. S. Armijo, J. R. Low, U. E. Wolff
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 462-477
Technical Paper | doi.org/10.13182/NT65-A20558
Influence of Preirradiation Heat Treatment on the Postirradiation Ductility of Stainless Steel
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 478-483
Technical Paper | doi.org/10.13182/NT65-A20559
Inhibition of Chloride Stress Corrosion Cracking of Austenitic Stainless Steel
C. R. Bergen
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 484-489
Technical Paper | doi.org/10.13182/NT65-A20560
Formation of Cyanide in Liquid Sodium
E. W. Hobart, R. G. Bjork
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 490-492
Technical Paper | Technical Note | doi.org/10.13182/NT65-A20561
Liquid-Metal Boiling Heat Transfer
Y. S. Tang
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 521-537
Technical Paper | doi.org/10.13182/NT65-A20579
Effective Resonance Temperature Correlation of UO2
William T. Sha
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 538-545
Technical Paper | doi.org/10.13182/NT65-A20580
A Nuclearly Safe Triangular-Slab Tank for Handling Enriched Uranium
C. E. Newlon, R. J. Clouse, A. J. Mallett
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 546-547
Technical Paper | doi.org/10.13182/NT65-A20581
Gamma-Ray-Induced Chlorination of Benzene
Richard E. Faw, John M. McCabe, Herbert S. Isbin
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 548-555
Technical Paper | doi.org/10.13182/NT65-A20582
Production of Carrier-Free 132Cs and 129Cs
Virginia H. Wilson, W. N. Bishop, Manny Hillman
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 556-559
Technical Paper | doi.org/10.13182/NT65-A20583
Pyrolytic-Carbon Coatings on Ceramic Fuel Particles
R. L. Beatty, F. A. Carlsen, Jr., J. L. Cook
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 560-566
Technical Paper | doi.org/10.13182/NT65-A20584
Fluidized-Bed Process for Production of Tungsten
J. H. Oxley, E. A. Beidler, J. M. Blocher, Jr., C. J. Lyons, R. S. Park, J. H. Pearson
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 567-574
Technical Paper | doi.org/10.13182/NT65-A20585
Vapor Deposition and Characterization of Tungsten-Rhenium Alloys
J. I. Federer, C. F. Leitten, Jr.
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 575-580
Technical Paper | doi.org/10.13182/NT65-A20586
Suppression of Grain Growth in Vapor-Deposited Tungsten up to 2500°C
A. F. Weinberg, J. R. Lindgren, N. B. Elsner, R. G. Mills
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 581-583
Technical Paper | doi.org/10.13182/NT65-A20587
Thermochemical Reduction of Uranium Hexafluoride for the Direct Fabrication of Uranium Dioxide Ceramic Fuels
R. L. Heestand, C. F. Leitten, Jr.
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 584-588
Technical Paper | doi.org/10.13182/NT65-A20588
Fabrication of 20wt%Ti-V Alloy Tubing for Nuclear Fuel Cladding
W. R. Burt, Jr., W. C. Kramer, F. J. Karasek, R. M. Mayfield
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 589-596
Technical Paper | doi.org/10.13182/NT65-A20589
Absolute Liquid-Scintillation Rate Constants and Fluorescence Efficiencies
H. R. Lukens, Jr.
Nuclear Technology | Volume 1 | Number 6 | December 1965 | Pages 597-602
Technical Paper | doi.org/10.13182/NT65-A20590