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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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Materials Performance In Nuclear Pressurized Water Reactor Steam Generators
Stanley J. Green, J. Peter N. Paine
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 10-29
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32828
Materials Performance in CANDU Nuclear Steam Generators
G. F. Taylor, D. P. Dautovich
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 30-36
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32829
Steam Generator Materials Performance in High Temperature Gas-Cooled Reactors
J. E. Chafey, D. I. Roberts
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 37-49
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32830
Experience In Operating Gas-Cooled Reactor Steam Generators of U.K. Design
D. W. James
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 50-59
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32831
Experience with Liquid-Metal Fast Breeder Reactor Steam Generators-U.S. Design
C. C. Stone, J. A. Ford, F. E. Tippets, J. S. McDonald, G. Grant, J. L. Epstein
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 60-87
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32832
Materials Requirements for Pressurized Water Reactor Steam Generator Tubing
Ph. Berge, J. R. Donati
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 88-104
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32833
Chemical Thermohydraulics of Steam Generating Systems
Paul Cohen
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 105-116
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32834
System Chemistry Considerations for Nuclear Steam Generators
Frederick, J. Pocock
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 117-123
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32835
The Implications for Condensate Purification of Operation at pH 9.6
R. Garnsey, D. J. Parry
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 124-134
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32836
Effects of Copper and Nickel Compounds on the Corrosion of Pressurized Water Reactor Steam Generator Materials
Earl L. White, Warren E. Berry
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 135-150
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32837
The Design and Construction of Boilers for Advanced Gas-Cooled Reactors in the United Kingdom
P. J. Cameron, J. Walters
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 151-162
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32838
Study on Hydrogen-Induced Cracking in the Heat-Affected Zone of Heavy Forgings Overlaid by Stainless Steel
K. Ohnishi, H. Tsukada, M. Kusuhashi, Y. Tanaka
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 163-177
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32839
Evaluation of Sodium Phosphate as A Denting Inhibitor
R. S. Pathania, E. G. McVey
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 178-190
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32840
Corrosion of Alloy 600 by Cationic Resin Beads
Martin W. Kendig, Hugh S. Isaacs
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 191-195
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32841
Pitting Corrosion of Nuclear Steam Generator Materials
P. J. King, D. P. Dautovich
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 196-206
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32842
Chemical Cleaning of the Nuclear Power Demonstration Unit Boiler
C. R. Frost, P. Walmsley, P. V. Balakrishnan, P. McSweeney
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 207-217
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32843
SNR 300 Experience in Steam Generator Materials
M. H. Knaap, H. C. D. Nieuwland, J. Vrijen, J. K. Van Westenbrugge, W. Husslage, C. P. Scheepens, J. W. Schinkel
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 218-227
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32844
Fabrication Technology—Liquid-Metal Fast Breeder Reactor Steam Generators
C. N. Spalaris, P. J. Ring, E. A. Wright
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 243-249
Technical Paper | Materials | doi.org/10.13182/NT55-243
Material Selection and Optimization for Post-SNR-300 Steam Generators
J. Vrijen, J. K. van Westenbrugge, L. van der Wiel, P. L. F. Rademakers, C. P. Scheepens, J. W. Schinkel
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 250-258
Technical Paper | Materials | doi.org/10.13182/NT55-250
Some Aspects of Materials Development for Sodium-Heated Steam Generators
Prodyot Roy, C. N. Spalaris
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 259-269
Technical Paper | Materials | doi.org/10.13182/NT55-259
Materials Development for a Fast Breeder Reactor Steam Generator Concept
C. E. Sessions, S. D. Reynolds, Jr., M. A. Hebbar, J. F. Lewis, J. H. Kiefer
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 270-279
Technical Paper | Materials | doi.org/10.13182/NT55-270
Steam Generator Tubing Development for Commercial Fast Breeder Reactors
C. E. Sessions, C. F. Uber
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 280-288
Technical Paper | Materials | doi.org/10.13182/NT55-288
Metallurgical Examination of Tube-to-Tube-Plate Welds Removed from Dounreay Prototype Fast Reactor Evaporators
G. R. Kirkland, E. R. Davies, M. E. Lambert, E. J. Kennett
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 289-301
Technical Paper | Materials | doi.org/10.13182/NT55-289
Effect of Decarburization on Structural and Mechanical Properties of Ferritic Steels
A. A. Tavassoli, H. Touron, M. Weisz
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 302-310
Technical Paper | Materials | doi.org/10.13182/NT55-302
Flow-Induced Vibration and Wear of Steam Generator Tubes
H. J. Connors
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 311-331
Technical Paper | Materials | doi.org/10.13182/NT55-311
Materials Property Requirements for Steam Generator Components in the Creep Range
D. S. Wood
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 332-338
Technical Paper | Materials | doi.org/10.13182/NT55-332
Water Chemistry of Breeder Reactor Steam Generators
J. L. Simpson, M. N. Robles, C. N. Spalaris, S. A. Moss
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 339-348
Technical Paper | Materials | doi.org/10.13182/NT55-339
A Chemical Cleaning Process for Nuclear Steam Generators
P. V. Balakrishnan, P. McSweeney, C. R. Frost, P. Walmsley
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 349-361
Technical Paper | Materials | doi.org/10.13182/NT55-349
Eddy Current Inspection of a 17-Year-Old Nuclear Steam Generator
G. van Drunen, V. S. Cecco
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 362-370
Technical Paper | Materials | doi.org/10.13182/NT55-362
Replacement of Damaged Steam Generator Tubing in 600-MW(electric) Canadian Deuterium Uranium Nuclear Plants
R. H. Renshaw, S. Roy
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 371-382
Technical Paper | Materials | doi.org/10.13182/NT55-371
Effect of Environmental Variables on the Stress Corrosion Cracking of Inconel 600 Steam Generator Tubing
T. S. Bulischeck, D. van Rooyen
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 383-393
Technical Paper | Materials | doi.org/10.13182/NT55-383
Effect of Heat Treatment on the Susceptibility to Stress Corrosion Cracking of Alloy 600
M. Kowaka, H. Nagano, T. Kudo, Y. Okada, M. Yagi, O. Takaba, T. Yonezawa, K. Arioka
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 394-404
Technical Paper | Materials | doi.org/10.13182/NT55-394
Model Boiler Inhibition Studies of the Nuclear Steam Generator Denting Phenomenon
C. R. Wolfe, J. N. Esposito, D. D. Whyte, J. M. Gilkison, J. R. Balavage, M. J. Wootten, S. M. Wozniak
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 405-421
Technical Paper | Materials | doi.org/10.13182/NT55-405
Materials Model Boiler Tests for the Babcock & Wilcox Once-Through Steam Generators
R. H. Emanuelson, D. F. Levstek, K. E. Moore, G. J. Theus
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 422-435
Technical Paper | Materials | doi.org/10.13182/NT55-422
A Stress Corrosion Cracking Evaluation of Inconel 690 for Steam Generator Tubing Applications
G. P. Airey, A. R. Vaia, R. G. Aspden
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 436-448
Technical Paper | Materials | doi.org/10.13182/NT55-436
The Stress Corrosion Cracking of 2 1/4 Cr—Mo Ferritic Steel in Caustic Environments
P. Hurst, H. C. Cowen
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 449-459
Technical Paper | Materials | doi.org/10.13182/NT55-449
Fretting and Wear of Stainless and Ferritic Steels in Liquid-Metal Fast Breeder Reactor Steam Generators
Michael W. J. Lewis, Charles S. Campbell
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 460-469
Technical Paper | Materials | doi.org/10.13182/NT55-460
Examination of Leaking Tube-to-Tube-Plate Welds from an Austenitic Steel Steam Generator Superheater in the Dounreay Prototype Fast Reactor
G. R. Kirkland, E. R. Davies, M. E. Lambert
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 470-478
Technical Paper | Materials | doi.org/10.13182/NT55-478
Creep Behavior Evaluation of Hastelloy X Welded Joint
Kunihiko Satoh, Masao Toyoda, Shigetomo Matsui, Eisuke Mori, Shigeki Shimizu, Keisuke Satoh
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 479-486
Technical Paper | Materials | doi.org/10.13182/NT55-479
On the Temper Embrittlement of Manganese-Molybdenum-Nickel Steels
S. G. Druce, B. C. Edwards
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 487-498
Technical Paper | Materials | doi.org/10.13182/NT55-487
A Study of Crack Initiation in Corrosion Fatigue of AISI Type 316 Stainless Steel by Dynamic Measurement of Corrosion Current Transients
J. W. Martin, D. E. J. Talbot
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 499-504
Technical Paper | Materials | doi.org/10.13182/NT55-504
Low Cycle Fatigue of Steam Generator Tubes in the Vicinity of Roll Joints
B. Mukherjee, M. H. El Haddad, M. L. Vanderglas, D. V. Leemans
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 505-512
Technical Paper | Materials | doi.org/10.13182/NT55-505
Studies of Denting of Steam Generators with Simulated Fresh Water In-Leakage
James Brown, Francisco Gonzalez, David Iley, Alexandra McKay
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 513-524
Technical Paper | Materials | doi.org/10.13182/NT55-513
Metallurgical Examination of Cracked Feedwater Pipes from Nine Pressurized Water Reactors
Brijesh Vyas, Carl J. Czajkowski, John R. Weeks
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 525-537
Technical Paper | Materials | doi.org/10.13182/NT55-525
Heterogeneous Poisoning of the Critical HTGR Test Facility Kahter: A Study for the Initial Loading of Pebble Bed Power Reactors
Volker Drüke, Detlef Filges, Rahim Nabbi, Ralf D. Neef, Norbert Paul, Hartwig Schaal
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 549-564
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32798
Spectral Effects in the Extrapolation of Pressure Vessel Surveillance Capsule Measurements
J. F. Carew, D. K. Min, A. L. Aronson
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 565-567
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32799
A Posteriori Evaluation of the Coarse-Mesh Calculation Results in Boiling Water Reactor Dynamics
Miroslav Havránek, Jochen Elzmann
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 568-577
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32800
Analysis of Manual Depressurization of a Boiling Water Reactor Under Transient Condition
Farid Bamdad
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 578-582
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32801
Fuel Cycle Extension by Part-Length Control Rod Removal at Rancho Seco
T. N. Ake, R. G. McAndrew, D. D. Whitney
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 583-586
Technical Paper | Fuel Cycle | doi.org/10.13182/NT81-A32802
Radial Concentration and Effect on Temperature of Plutonium Formed in UO2 During Irradiation
H. Carlsen, D. N. Sah
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 587-593
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32803
Fuel Motion in Experiments Simulating Liquid-Metal Fast Breeder Reactor Loss-of-Flow Accidents
Richard Simms, George S. Stanford, Charles L. Fink, James P. Regis
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 594-600
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32804
Vitrification of Simulated High-Level Radioactive Waste by a Slurry-Fed Ceramic Melter
G. G. Wicks
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 601-606
Technical Paper | Redioactive Waste Managment | doi.org/10.13182/NT81-A32805
Economic Impact of Nuclear Core Materials Limitations
David G. Franklin
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 607-616
Technical Paper | Economic | doi.org/10.13182/NT81-A32806
Design, Production, and Evaluation of a Zircaloy-Clad Uranium Target for an Intense Pulsed Neutron Source Application
B. A. Loomis, H. R. Thresh, G. L. Fogle, S. B. Gerber
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 617-627
Technical Paper | Material | doi.org/10.13182/NT81-A32807
The Effects of Texture and Surface Condition on the Iodine Stress Corrosion Cracking Susceptibility of Unirradiated Zircaloy-2
B. C. Syrett, D. Cubicciotti, R. L. Jones
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 628-641
Technical Paper | Material | doi.org/10.13182/NT81-A32808
A Design Study of the Neutron Irradiation Facility for Boron Neutron Capture Therapy
Yoshiaki Oka, Ichiroh Yanagisawa, Shigehiro
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 642-655
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT81-A32809
Thermal Response of a Flat Plate of Finite Thickness Immersed in a Fluid with Oscillating Temperature
A. M. Poindexter
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 656-661
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32810
Optimization of a Variable Flow Allocation Scheme in Heterogeneous Liquid-Metal Fast Breeder Reactors
Constantine P. Tzanos
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 662-673
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32811
Automated In-Line Measurement of Plutonium Solutions in a Plutonium Purification Process
T. K. Li
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 674-682
Technical Paper | Analyse | doi.org/10.13182/NT81-A32812
Weighing of Heavy Vessels Using Strain Gauges
J. P. Ruiter
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 683-689
Technical Paper | Technique | doi.org/10.13182/NT81-A32813
The Critical Safety Functions and Plant Operation
William R. Corcoran, Nancy J. Porter, James F. Church, Michael T. Cross, Walter M. Guinn
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 690-712
Technical Paper | Education | doi.org/10.13182/NT81-A32814
A Fast Reactor Core Concept Using an Internal Blanket
Katsuyuki Kawashima, Kotaro Inoue, Setsuo Kobayashi
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 713-719
Technical Note | Fission Reactor | doi.org/10.13182/NT81-A32815
Influence of Surface Condition on Crack Initiation in Iodine-Induced Stress Corrosion Cracking of Zircaloys
Daniel Cubicciotti, B. C. Syrett, R. L. Jones
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 720-723
Technical Note | Material | doi.org/10.13182/NT81-A32816
Source Imaging Using Neutron Pinhole Cameras Based on Position-Sensitive Proportional Counters
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 724-727
Technical Note | Technique | doi.org/10.13182/NT81-A32817