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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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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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Physics of Nuclear Materials Safeguards Techniques
Tsahi Gozani
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 8-19
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Reactor | doi.org/10.13182/NT72-A31093
Near Barrier Fission Induced with Photons
John R. Huizenga
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 20-32
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Reactor | doi.org/10.13182/NT14-1-20
Low Energy Photofission of Heavy Elements—Experimental Results
R. L. Bramblett, T. Gozani, R. O. Ginaven, D. E. Rundquist
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 33-41
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Reactor | doi.org/10.13182/NT72-A31095
Theory of Delayed-Neutron Physics
L. Tomlinson
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 42-52
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Reactor | doi.org/10.13182/NT72-A31096
Physics of Delayed Neutrons—Recent Experimental Results
G. Robert Keepin
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 53-58
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Reactor | doi.org/10.13182/NT72-A31097
Application of Neutron Techniques in the Nondestructive Assay of Fissile Materials
D. Stegemann
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 59-64
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Reactor | doi.org/10.13182/NT72-A31098
A Model for the High Temperature Swelling of Clad Oxide Fuel
Arthur A. Bauer
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 65-70
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Fuel | doi.org/10.13182/NT72-A31099
Some Effects of Water Sprinklers on Array Criticality Safety Analyses
G. R. Handley
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 71-75
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Fuel | doi.org/10.13182/NT72-A31100
In Situ Incorporation of Nuclear Waste in Deep Molten Silicate Rock
Jerry J. Cohen, Arthur E. Lewis, Robert L. Braun
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 76-88
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Radioactive Waste | doi.org/10.13182/NT72-A31101
The Atomic Energy Research Establishment Miniature Nuclear Battery
A. W. Penn, M. H. Brown, J. Myatt, M. J. Poole
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 89-95
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Radioisotope | doi.org/10.13182/NT72-A31102
Copper Assay of Biomaterials with Neutron Activation
N. Spronk, R. J. Van Hoek
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 96-104
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Analysis | doi.org/10.13182/NT72-A31103
Precision and Source of Variation of Oxygen-to-Metal Determinations for (U, Pu)O2
W. J. Lackey, R. A. Bradley, W. H. Pechin, T. L. Hebble
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 105-107
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Material | doi.org/10.13182/NT72-A31104
Optimal Operational Strategy in Nuclear Fuel Management
P. Civita, P. Fornaciari, T. Mazzanti
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 116-122
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31126
Pressurized Water Reactor Optimal Fuel Management
Barry N. Naft, Alexander Sesonske
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 123-132
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31127
First Loss of Flow Experiment with an FTR-Type Fuel Pin in the Mark-II Loop
J. C. Carter, R. T. Purviance, J. F. Boland, C. E. Dickerman, J. E. Hanson
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 133-145
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31128
Fuel Rod Enrichment Determination By Gamma-Ray Spectrometry
A. D. Vaughn, R. I. Smith
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 146-152
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31129
A Simple Method of Calculating the Radial Temperature Distribution in a Mixed-Oxide Fuel Element
R. O. Meyer, B. J. Buescher
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 153-156
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31130
Radioactive Waste Management and Radiation Exposure
Morton I. Goldman
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 157-162
Technical Paper | Radioactive waste | doi.org/10.13182/NT72-A31131
The Effect of Stress Ratio on the Elevated Temperature Fatigue-Crack Propagation of Type 304 Stainless Steel
Lee A. James
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 163-170
Technical Paper | Materlal | doi.org/10.13182/NT72-A31132
In-Pile Dimensional Changes of Zircaloy-4 Tubing Having Low Hoop Stresses (Light Water Breeder Reactor Development Program)
Ray C. Daniel
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 171-186
Technical Paper | Material | doi.org/10.13182/NT72-A31133
Project Rulison—Summary of Results and Analyses
Miles Reynolds, Jr.
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 187-193
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT72-A31134
Note on Detectability Enhancement of Weak Neutron Burst Signals Through Multiplication
K. G. Porges
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 194-196
Technical Note | Instrument | doi.org/10.13182/NT72-A31135
Measurement of the Uranium-235 Content in a Spent Mtr Type Fuel Element Using the Delayed-Neutron Yield Technique
R. H. Augustson, C. N. Henry, C. R. Weisbin
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 197-199
Technical Note | Analysis | doi.org/10.13182/NT72-A31136
Vector Analysis of Time-Dependent Gamma-Ray Spectra
W. L. Filippone, F. J. Munno
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 200-202
Technical Note | Analysis | doi.org/10.13182/NT72-A31137
The Use of Signal Coherence for Anomaly Detection in Nuclear Reactors
Robert W. Albrecht
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 208-217
Technical Paper | Reactor | doi.org/10.13182/NT72-A31110
Steam Generator Vessel Pressures Resulting from a Sodium-Water Reaction—A Computer Analysis with the SWEAR Code
David A. Greene
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 218-231
Technical Paper | Reactor | doi.org/10.13182/NT72-A31111
New Perspectives on Low Level Environmental Radiation Monitoring Around Nuclear Facilities
H. L. Beck, J. A. DeCampo, C. V. Gogolak, W. M. Lowder, J. E. McLaughlin, arid P. D. Raft
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 232-239
Technical Paper | Reactor Siting | doi.org/10.13182/NT72-A31112
The Effects of Transverse Flow Through Graphite on Fission Product Movement in HTGR-Type Systems
M. N. Özişik, M. D. Silverman
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 240-246
Technical Paper | Fuel | doi.org/10.13182/NT72-A31113
An Analytical Method for Calculating Steady-State Fission Gas Release
V. F. Baston, J. H. McFadden, W. A. Yuill
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 247-256
Technical Paper | Fuel | doi.org/10.13182/NT72-A31114
Microstructure of Sol-Gel-Derived (U, Pu)O2 Microspheres and Pellets
W. J. Lackey, R. A. Bradley
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 257-268
Technical Paper | Fuel | doi.org/10.13182/NT72-A31115
Electronic Assay of Californium-252 Neutron Sources
T. R. Herold
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 269-278
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31116
Thermal-Neutron Radiography with a Sealed-Tube Neutron Generator and Water Moderator
Dennis G. Vasilik, Richard L. Murri, George P. Fisher
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 279-283
Technical Paper | Instrument | doi.org/10.13182/NT72-A31117
Measurement of Fast- and Thermal-Neutron Fluxes Using a Small LiI(Eu) Crystal Detector
Dong H. Nguyen, Robert G. Bennett
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 284-291
Technical Paper | Instrument | doi.org/10.13182/NT72-A31118
An Empirical Representation of Irradiation-Induced Swelling of Solution Treated Type 304 Stainless Steel
J. F. Bates, J. L. Straalsund
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 292-298
Technical Note | Material | doi.org/10.13182/NT72-A31119
