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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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Fusion Science and Technology
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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The SEFOR Minimum Critical Core
L. D. Noble, P. Greebler, G. R. Pflasterer, Jr., B. U. B. Sarma, D. Wintzer
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 5-10
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30941
Fission Products in Reactor Dynamics
Jan S. Woyski
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 11-16
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30942
The Effect of a Metallurgical Phase Change in Fuel on the Power Coefficient of EBR-II
John K. Long
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 17-21
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30943
A Proposal for Using Nuclear Reactors as Thermal Radiation Sources
K. Almenas
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 22-32
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30944
On-Line Noble Gas Fission Product Monitoring in Experimental Breeder Reactor II
G. S. Brunson
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 33-43
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30945
Prediction of the Irradiation Performance of. Coated Particle Fuels by Means of Stress-Analysis Models
J. L. Kaae, D. W. Stevens, C. S. Luby
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 44-53
Technical Paper and Note | Fuel | doi.org/10.13182/NT71-A30946
Thermal Expansion of Uranium and Tantalum Monocarbides up to 2700°C
Hans K. Richards
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 54-61
Technical Paper and Note | Fuel | doi.org/10.13182/NT71-A30947
Development of an Ultrafine Grain Size Type-316 Stainless-Steel Cladding
G. A. Reimann
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 62-66
Technical Paper and Note | Fuel | doi.org/10.13182/NT71-A30948
Analysis of Corrosion of Stainless Steel in a Sodium and High Radiation Environment
J. N. Anno, J. A. Walowit
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 67-75
Technical Paper and Note | Material | doi.org/10.13182/NT71-A30949
Ionizing Radiation Effects in Lithium Niobate
William Primak, T. T. Anderson, S. L. Halverson
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 76-84
Technical Paper and Note | Radiation | doi.org/10.13182/NT71-A30950
A Dual Spectrum Concept for LMFBR Fuel Assay
Charles Kelber
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 85-90
Technical Paper and Note | Technique | doi.org/10.13182/NT71-A30951
Experiences with Dynamic Testing Methods at the Molten-Salt Reactor Experiment
T. W. Kerlin, S. J. Ball, R. C. Steffy, M. R. Buckner
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 103-117
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30919
Theoretical Dynamics Analysis of the Molten-Salt Reactor Experiment
T. W. Kerlin, S. J. Ball, R. C. Steffy
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 118-132
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30920
A Small Nuclear Reactor for Undersea Use
Carroll B. Mills
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 133-138
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30921
The Instrumented Subassembly System in Ebr-II
A. Smaardyk, C. J. Divona, E. Hutter
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 139-159
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30922
Calculation of Neutron Detector Response in a Subcritical Reactor
W. R. Waltz, J. F. Walter
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 160-167
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30923
Short-Interval Series Pulsing—Experimental Studies and Numerical Experiments
H. A. Kurstedt, Jr., G. H. Miley
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 168-178
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30924
An Empirical Model for Safe Pipe Intersections Containing Fissile Solution
Deanne Dickinson, C. L. Schuske
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 179-187
Technical Paper and Note | Chemical Processing | doi.org/10.13182/NT71-A30925
Very Intense Neutron Source
R. M. Brugger, G. J. Russell, B. W. Johnson, G. P. DeVault†
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 188-203
Technical Paper and Note | Accelerator | doi.org/10.13182/NT71-A30926
Construction Materials for Neutron Capture-Gamma-Ray Measurement Assembly Using Californium-252
F. E. Senftle, A. G. Evans, D. Duffey, P. F. Wiggins
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 204-210
Technical Paper and Note | Instrument | doi.org/10.13182/NT71-A30927
Detection and Location of Leaking Triga Reactor Fuel Elements
G. D. Bouchey, S. J. Gage
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 211-214
Technical Paper and Note | Instrument | doi.org/10.13182/NT71-A30928
A Simple Total-Reflecting Low-Energy Neutron Spectrometer
Werner Fiala, Carlos V. Wheeler
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 215-220
Technical Paper and Note | Instrument | doi.org/10.13182/NT71-A30929
Self-Auditing Multichannel Neutron Monitor
W. F. Splichal, Jr.
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 221-223
Technical Paper and Note | Instrument | doi.org/10.13182/NT71-A30930
Neutron Activation Analysis of Inorganic Constituents of Airborne Particulates
K. K. S. Pillay, C. C. Thomas, Jr., C. M. Hyche
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 224-231
Technical Paper and Note | Analysis | doi.org/10.13182/NT71-A30931
Formation of Intimate Oxide-Carbon Mixtures of Fuel Materials as an Intermediate for Carbide and Nitride Fuels
E. A. Coppinger, B. M. Johnson
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 232-236
Technical Paper and Note | Chemical Processing | doi.org/10.13182/NT71-A30932
A Fast Reactor Assessment Study
Reino Ekholm
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 249-256
Technical Paper | Reactor | doi.org/10.13182/NT71-A30957
Prediction of Three-Dimensional Core Performance of JPDR (A BWR) for Burnup Cases
T. Shimooke
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 257-272
Technical Paper | Reactor | doi.org/10.13182/NT71-A30958
Experience in Reactor Malfunction Diagnosis Using On-Line Noise Analysis
D. N. Fry
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 273-282
Technical Paper | Reactor | doi.org/10.13182/NT71-A30959
Preparation of Sol-Gel Spheres Smaller than 200 Microns without Fluidization
P. A. Haas
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 283-292
Technical Paper | Fuel | doi.org/10.13182/NT71-A30960
A Study of Noncondensable Effects in a Heat Pipe
G. T. Colwell, C. L. Williams, J. C. Hsu, G. E. Zevallos
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 293-300
Technical Paper | Fuel | doi.org/10.13182/NT71-A30961
An Explicit Solution for Stresses in Pyrocarbon-Coated Fuel Particles
D. W. Stevens
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 301-306
Technical Paper | Fuel | doi.org/10.13182/NT71-A30962
Carbon Transport in Flowing Sodium
Prodyot Roy, Gary P. Wozadlo
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 307-314
Technical Paper | Material | doi.org/10.13182/NT71-A30963
Generation of a Low-Energy Positron Beam
Günter H. Lohnert, Richard T. Schneider
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 315-321
Technical Paper | Radioisotope | doi.org/10.13182/NT71-A30964
The Preparation and Properties of LiPb, a Novel Material for Shields and Collimators
Norman A. Frigerio, Leo L. LaVoy
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 322-324
Technical Paper | Shielding | doi.org/10.13182/NT71-A30965
Bremsstrahlung Shielding from Electron Trapping in Dielectrics
D. L. Hollis
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 325-327
Technical Paper | Shielding | doi.org/10.13182/NT71-A30966
Corrections for Dead-Time Losses in the Measurement of Gamma-Ray Spectra of Short-Lived Radionuclides
H. A. Das, J. Zonderhuis
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 328-334
Technical Paper | Instrument | doi.org/10.13182/NT71-A30967
An Electrochemical Carbon Meter for Use in Sodium
F. J. Salzano, L. Newman, M. R. Hobdell
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 335-347
Technical Paper | Instrument | doi.org/10.13182/NT71-A30968
Prediction of Nuclear Weapon Neutron-Radiation Environments
R. L. French, L. G. Mooney
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 348-365
Technical Paper | Radiation | doi.org/10.13182/NT71-A30969
A Multi-Spectra Neutron Irradiation Technique for the Nondestructive Assay of Fissionable Materials
H. O. Menlove, R. H. Augustson, Darryl B. Smith
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 366-379
Technical Paper | Analysis | doi.org/10.13182/NT71-A30970
Use of Simulation Plus Real Steam Turbine for Teaching Theory and Operation of a Pressurized Water Reactor
M. A. Schultz, Wayne F. Eckley
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 380-390
Technical Paper | Education | doi.org/10.13182/NT71-A30971
A Technical Note on D-T Fusion Reactor Afterheat
Donald J. Dudziak
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 391-392
Technical Note | Reactor | doi.org/10.13182/NT71-A30972
Design of Spray Additive Systems
J. L. Gallagher, L. D. Green, R. T. Marchese
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 406-411
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16249
Drop Size Distribution and Spray Effectiveness
W. F. Pasedag, J. L. Gallagher
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 412-419
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16250
Post-LOCA Hydrogen Generation in PWR Containments
W. D. Fletcher, M. J. Bell, R. T. Marchese, J. L. Gallagher
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 420-427
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16251
Iodine Removal in the Ice Condenser System
D. D. Malinowski, L. F. Picone
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 428-435
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16252
Radiation and Thermal Stability of Spray Solutions
H. E. Zittel, T. H. Row
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 436-443
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16253
Sodium Thiosulfate Spray System for Radioiodine Removal
W. E. Joyce*
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 444-448
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16254
Stability of Thiosulfate Spray Solutions
W. N. Bishop, D. A. Nitti
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 449-453
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16255
Post-Accident Hydrogen Generation and Control
D. W. LaBelle
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 454-459
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16256
A Study of the Absorption of CH3I by Aqueous Spray Solutions
B. A. Soldano, W. T. Ward
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 460-465
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16257
Studies on Iodine Trapping by Water Systems at Studsvik
L. Devell, R. Hesböl, E. Bachofner*
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 466-471
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16258
Spray Program at the Nuclear Safety Pilot Plant
L. F. Parsly
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 472-485
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16259
Removal of Iodine from Atmosphere by Sprays
Y. Nishizawa, S. Oshima, T. Maekawa
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 486-498
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16260
Removal of Iodine and Particles by Sprays in the Containment Systems Experiment
R. K. Hilliard, A. K. Postma, J. D. McCormack,*, L. F. Coleman**
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 499-519
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16261
Scalbatraio Center for Research in Nuclear Safety
B. Guerrini, S. Lanza, M. Mazzini, R. Mirandola
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 520-537
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16262
Protective Coatings (Paints) for PWR and BWR Reactor Containment Facilities
C. D. Watson, J. C. Griess, T. H. Row, G. A. West
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 538-545
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16263
The Corrosion of Materials in Reactor Containment Spray Solutions
J. C. Griess, A. L. Bacarella
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 546-553
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16264
Nuclear Energy Costs and Economic Development, Proceedings of a Symposium in Istanbul, October 1969
Pablo Mulás del Pozo
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 554-555
Department | Symposium on Reactor Containment Spray System Technology / Book Review | doi.org/10.13182/NT71-A16265
Random Noise Techniques in Nuclear Reactor Systems
Lynn Weaver
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Page 555
Department | Symposium on Reactor Containment Spray System Technology / Book Review | doi.org/10.13182/NT71-A16266
