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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Technology
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Latest News
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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Nuclear Design of the Blanket/Shield System for a Tokamak Experimental Power Reactor
Mohamed A. Abdou
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 7-36
Technical Paper | Reactor | doi.org/10.13182/NT76-A16287
Development of Improved Data Analysis Methods for Reactivity Measurements in Large Thermal-Power Reactors
K. L. Ferguson, C. G. Poncelet, and A. J. Impink, Jr.
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 37-52
Technical Paper | Reactor | doi.org/10.13182/NT76-A16288
Effect of Fallout on Measurement of Iodine-131 Around Nuclear Reactors
C. J. Paperiello, J. M. Matuszek
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 53-56
Technical Paper | Reactor Siting | doi.org/10.13182/NT76-A16289
Livermore Plutonium Array Program: Experiments and Calculations
O. C. Kolar, H. F. Finn, N. L. Pruvost
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 57-72
Technical Paper | Fuel Cycle | doi.org/10.13182/NT76-A16290
Effects Due to Fission Gas During Unprotected Overpower Transients in a Liquid-Metal Fast Breeder Reactor
H. G. Bogensberger, C. Ronchi
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 73-85
Technical Paper | Fuel | doi.org/10.13182/NT76-A16291
High Strain Crack Growth in Zircaloy-2 Welds
H. D. Solomon
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 86-93
Technical Paper | Material | doi.org/10.13182/NT76-A16292
Stainless-Steel Weight Loss in Nitrogen-Contaminated Liquid Lithium
R. J. Schlager, R. A. Patterson, D. L. Olson, W. L. Bradley
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 94-97
Technical Paper | Material | doi.org/10.13182/NT76-A16293
Calculated Composition Changes of Some Refractory Metals in a Fusion Reactor Environment
D. S. Kopecki, K. M. Ralls, E. Linn Draper, Jr.
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 98-107
Technical Paper | Material | doi.org/10.13182/NT76-A16294
Two-Up, One-Down Ideal Cascades for Isotope Separation
Donald R. Olander
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 108-112
Technical Paper | Isotope Separation | doi.org/10.13182/NT76-A16295
In-Pile Gamma-Ray Spectrometry to Follow OSIRIS Irradiations
G. Farny, M. Destot, D. Texier, J. L. Faugere, M. Mouchnino
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 113-123
Technical Paper | Instrument | doi.org/10.13182/NT76-A16296
Welding Plastics by the Neutron Capture Process
J. N. Anno
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 124-126
Technical Paper | Radiation | doi.org/10.13182/NT76-A16297
Acoustic Emission Analysis of Stress Corrosion Cracking in Type 304 Stainless Steels
Jaishanker Shrinivasan Brihmadesam, N. J. McCormick
Nuclear Technology | Volume 29 | Number 1 | April 1976 | Pages 127-135
Technical Paper | Technique | doi.org/10.13182/NT76-A16298
Recent Concerns with Reactor Coolant Chemistry Technology in Pressurized Water Reactors
J. H. Hicks
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 146-152
Technical Paper | Material | doi.org/10.13182/NT76-A31573
Chemistry Experience in the Primary Heat Transport Circuits of Kraftwerk Union Pressurized Water Reactors
R. Riess
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 153-159
Technical Paper | Material | doi.org/10.13182/NT76-A31574
Ammonia Suppresses Oxygen Production in Boiling Water Reactors
J. E. LeSurf, G. M. Allison
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 160-165
Technical Paper | Material | doi.org/10.13182/NT76-A31575
Measurement of Fuel Element Crud Deposits in Pressurized Water Reactors
Yale Solomon, Josef Roesmer
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 166-173
Technical Paper | Material | doi.org/10.13182/NT76-A31576
The Application of Advanced Gas Cooled Reactor Materials
L. Henderson, R. Stead
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 174-190
Reactor | doi.org/10.13182/NT76-A31577
A Man-Machine Communication System for Boiling Water Reactor Core Management Planning
Osamu Yokomizo, Hiroshi Motoda, Takashi Kiguchi, Renzo Takeda
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 191-199
Fuel Cycle | doi.org/10.13182/NT76-A31578
Gas Tag Identification of Failed Reactor Assemblies—III. Tag Ratios for the Fast Flux Test Facility Cores I Through IV
N. J. McCormick, R. E. Schenter, R. P. Omberg
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 200-208
Fuel | doi.org/10.13182/NT76-A31579
Liquid Lithium Penetration of Stressed Armco Iron
W. Jordan, W. L. Bradley, D. L. Olson
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 209-214
Material | doi.org/10.13182/NT76-A31580
Reaction of Europia with Austenitic Stainless Steel
Paul C. S. WU
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 215-221
Material | doi.org/10.13182/NT76-A31581
Radioisotope Battery Using Schottky Barrier Devices
F. K. Manasse, A. N. Tse
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 222-238
Radioisotope | doi.org/10.13182/NT76-A31582
Estimation of Irradiation History of a Spent Fuel by Gamma-Ray Spectroscopy
Kanji Tasaka
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 239-248
Analysis | doi.org/10.13182/NT76-A31583
Effect of Neutron Irradiation on the Critical Current of Nb3Sn at High Magnetic Fields
C. L. Snead, Jr., Don M. Parkin
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 264-267
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31591
The Effect of Aluminum Additions on Nb3Sn Produced in the Solid State
David Dew-Hughes, Thomas S. Luhman, Masaki Suenaga
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 268-273
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31592
Ceramic Materials for Fusion
L. H. Rovner, G. R. Hopkins
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 274-302
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31593
Helium Blistering of Ceramic Coatings on Hastelloy X and Nb—1% Zr
M. Kaminsky, S. K. Das, R. Ekern
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 303-308
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31594
Vaporization Thermodynamics and Molecular Sputtering of Binary Targets
Dieter M. Gruen, Patricia A. Finn, Dennis L. Page
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 309-317
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31595
Sputtering Measurements on Controlled Thermonuclear Reactor Materials Using Auger Electron Spectroscopy
Joe N. Smith, Jr., C. H. Meyer, Jr., J. K. Layton
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 318-321
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31596
Low-Energy Proton Implantation of Stainless Steel
K. L. Wilson, G. J. Thomas, W. Bauer
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 322-326
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31597
An Intense Li(d,n) Neutron Radiation Test Facility for Controlled Thermonuclear Reactor Materials Testing
P. Grand, K. Batchelor, J. P. Blewett, A. Goland, D. Gurinsky, J. Kukkonen, C. L. Snead, Jr.
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 327-336
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31598
Controlled Thermonuclear Reactor Neutron Spectra Simulation at the LAMPF Radiation Effects Facility
M. L. Simmons, Donald J. Dudziak
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 337-345
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31599
Neutron-Energy-Dependent Defect Production Cross Sections for Fission and Fusion Applications
G. R. Odette, D. R. Doiron
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 346-368
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31600
Helium Charging of Metals by Tritium Decay
J. F. Remark, A. B. Johnson, Jr., Harry Farrar, IV, D. G. Atteridge
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 369-377
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31601
Effects of Helium on Void Swelling in Vanadium
J. L. Brimhall, E. P. Simonen
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 378-383
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31602
The Calculated Performance of Various Structural Materials in Fusion-Reactor Blankets
M. L. Williams, R. T. Santoro, T. A. Gabriel
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 384-391
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31603
A High-Gain Fusion-Fission Reactor for Producing Uranium-233
Shang-Fon Su, Gene L. Woodruff, N. J. McCormick
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 392-405
Technical Paper | Fusion Reactor Material / Reactor | doi.org/10.13182/NT76-A31604
Effects of Helium Mixing and Heat Transfer on Containment Design Pressure in a High-Temperature Gas-Cooled Reactor
John R. McCarty, Michael J. Kolar
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 406-414
Technical Paper | Fusion Reactor Material / Reactor | doi.org/10.13182/NT76-A31605
Considerations in the Design of Electron-Beam-Induced Fusion Reactor Systems
Samuel G. Varnado, Gary A. Carlson
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 415-427
Technical Paper | Fusion Reactor Material / Reactor | doi.org/10.13182/NT76-A31606
Determination of the Specific Heat Transfer Between Fuel and Canning from Reactivity Measurements at the Nuclear Pow er Plant KCB
H. Raum, G. Bronner, W. D. Krebs
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 428-432
Technical Paper | Fusion Reactor Material / Fuel | doi.org/10.13182/NT76-A31607
Development of Direct-Electrical-Heating Apparatus to Study the Response of Nuclear Fuels to Applied Transients
B. J. Wrona, E. Johanson
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 433-422
Technical Paper | Fusion Reactor Material / Instrument | doi.org/10.13182/NT76-A31608
