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Division Spotlight
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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Identification of Nuclear Systems
T. W. Kerlin, G. C. Zwingelstein, B. R. Upadhyaya
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 7-38
Technical Paper | Critical Review | doi.org/10.13182/NT77-A31954
Radiation Qualification of Nuclear Reactor Components
J. A. Naber, N. A. Lurie
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 40-47
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31956
Normal Operating Radiation Levels in Pressurized Water Reactor Plants
J. Sejvar
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 48-55
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31957
Calculation of Accident Doses to Equipment Inside Containment of Powe Reactors
Michael J. Kolar, Nolan C. Olson
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 56-64
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31958
Consideration of the Effect of Iodine Plateout on Containment Post-Loss-of-Coolant Accident Doses
Eugene Normand
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 65-73
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31959
Post-Loss-of-Coolant Accident Doses to Pressurized Water Reactor Equipment
Michael J. Kolar, John R. McCarty, Nolan C. Olson
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 74-78
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31960
Stability of Lithium Niobate on Irradiation at Elevated Temperature
William Primak, A. P. Gavin, T. T. Anderson, Emmet Monahan
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 79-84
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31961
A Possible Mechanism for Corrosion Product Transport and Radiation Field Growth in a Pressurized Water Reactor Primary Circuit
K. A. Burrill
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 85-92
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31962
Nuclear Reactor Control System Design with Sensor Failure
L. F. Miller, R. G. Cochran, J. W. Howze
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 93-105
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31963
Conversion of Waste Zircaloy Hulls to Zirconate Ion Exchange Materials for Waste Stabilization
H. S. Levine, E. J. Nowak
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 106-119
Radiation Environments in Nuclear Reactor Power Plant | Chemical Processing | doi.org/10.13182/NT77-A31964
The Production of Molten UO2 Pools by Internal Heating: Apparatus and Preliminary Experimental Heat Transfer Results
M. G. Chasanov, W. H. Gunther, L. Baker, Jr.
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 120-128
Radiation Environments in Nuclear Reactor Power Plant | Fuel | doi.org/10.13182/NT77-A31965
On the Simulation of Fast Breeder Reactor Pin Behavior Using UO2 Pins with Direct Electrical Heating
A. Alexas
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 129-138
Radiation Environments in Nuclear Reactor Power Plant | Fuel | doi.org/10.13182/NT77-A31966
Calculation of the Fragmentation of UO2 by Capacitor Discharge: Nonequilibrium Model
R. G. Alsmiller, Jr., R. B. Perez, J. Barish
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 139-147
Technical Note | Material | doi.org/10.13182/NT77-A31967
Comparison of Measured and Calculated Nitrogen-16 Activity in Water for Application to Nuclear-Powered Ship Reactor Designs
J. B. Sun, H. D. Warren
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 249-261
Technical Paper | Reactor | doi.org/10.13182/NT77-A31939
Design Considerations for Large Heterogeneous Liquid-Metal Fast Breeder Reactors
Constantine P. Tzanos, W. P. Barthold
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 262-274
Technical Paper | Reactor | doi.org/10.13182/NT77-A31940
A Practical Means for Pressure Transducer Response Verification
David G. Cain, Carleton G. Foster
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 275-284
Technical Paper | Reactor | doi.org/10.13182/NT77-A31941
Energy Optimization of a Cycled Tokamak
Peter S. Martini, Ronald J. Onega
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 285-293
Technical Paper | Reactor | doi.org/10.13182/NT77-A31942
Feasibility Study of Core Management System by Data Communication for Boiling Water Reactors
Hiroshi Motoda, Satoshi Tanisaka, Takashi Kiguchi, Haruo Yonenaga
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 294-304
Technical Paper | Fuel Cycle | doi.org/10.13182/NT77-A31943
Computation Studies of Cladding Relocation Dynamics During Liquid-Metal Fast Breeder Reactor Transient Undercooling Accidents
G. Angerer
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 305-313
Technical Paper | Fuel | doi.org/10.13182/NT77-A31944
Solid Waste as Refuse-Derived Fuel
R. Fred Rolsten, Leon Glaspell, J. P. Waltz
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 314-327
Technical Paper | Economic | doi.org/10.13182/NT77-A31945
An Optimal Set of Selected Uranium Enrichments That Minimizes Blending Consequences
Joel A. Nachlas, Harold A. Kurstedt, Jr., John S. Lorber, Jr.
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 328-335
Technical Paper | Economic | doi.org/10.13182/NT77-A31946
Damage Function for the Mechanical Properties of Steels
A. Alberman, J. P. Genthon, L. Salon, G. Allegraud
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 336-346
Technical Paper | Material | doi.org/10.13182/NT77-A31947
Stress-Free Swelling in Type 304 Stainless Steel at High Fluences
T. A. Kenfield, W. K. Appleby, H. J. Busboom
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 347-352
Technical Paper | Material | doi.org/10.13182/NT77-A31948
The Creep-Rupture Properties of a Weld-Overlaid Type 304 Stainless-Steel Forging
R. L. Klueh, D. A. Canonico
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 353-367
Technical Paper | Material | doi.org/10.13182/NT77-A31949
Fission Rate Measurements with the Makrofol Solid-State Track Recorder
Dariush Azimi-Garakani, John Garnett Williams
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 368-378
Technical Paper | Technique | doi.org/10.13182/NT77-A31950
Preparing the Implementation of Non-Proliferation Treaty Safeguards in the U.S.
Wolfgang Frenzel, Vladimir Shmelev, Adolf Von Baeckmann
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 158-162
Technical Paper | International Safeguard / Fuel Cycle | doi.org/10.13182/NT77-A31921
Report on an International Atomic Energy Agency Inventory Verification
George H. Winslow, A. Lee Harkness
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 163-166
Technical Paper | International Safeguard / Fuel Cycle | doi.org/10.13182/NT77-A31922
The Use of Fuel Reprocessing Plant Instrumentation for International Safeguards
Arnold L. Ayers
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 167-170
Technical Paper | International Safeguard / Fuel Cycle | doi.org/10.13182/NT77-A31923
Impurity Radiation from Medium Density Plasmas
G. R. Hopkins, John M. Rawls
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 171-186
Technical Paper | International Safeguard / Reactor | doi.org/10.13182/NT77-A31924
Radiographic Control of Materials Testing Reactor Fuel on X-Ray Paper
J. C. Domanus
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 187-192
Technical Paper | International Safeguard / Reactor | doi.org/10.13182/NT77-A31925
A Neutron-Gamma Chemonuclear Fusion Reactor
VI-Duong Dang, Meyer Steinberg
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 193-199
Technical Paper | International Safeguard / Reactor | doi.org/10.13182/NT77-A31926
Intrusion of Molten Steel into Cracks in Solid Fuel in a Transient-Undercooling Accident in a Liquid-Metal Fast Breeder Reactor
R. W. Ostensen, W. F. Murphy, B. J. Wrona, L. W. Deitrich, J. C. Florek
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 200-214
Technical Paper | International Safeguard / Reactor | doi.org/10.13182/NT77-A31927
The Isolation of Radioiodine with Portland Cement. Part I: Scoping Leach Studies
Walter E. Clark
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 215-221
Technical Paper | International Safeguard / Chemical Processing | doi.org/10.13182/NT77-A31928
Differences in the 103Ru and 106Ru Axial Distributions in (U,Pu)O2 Fuel Pins
J. R. Phillips, T. K. Marshall
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 222-228
Technical Paper | International Safeguard / Fuel | doi.org/10.13182/NT77-A31929
Reactor Hydrodynamics During the Reflood Phase of a Loss-of-Coolant Accident
Rodney R. Gay
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 229-237
Technical Note | International Safeguard / Reactor | doi.org/10.13182/NT77-A31930
