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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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 Science and Engineering
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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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Probabilistic Analysis of the Interfacing System Loss-of-Coolant Accident and Implications on Design Decisions
F. L. Leverenz, Jr., A. A. Garcia, J. E. Kelly
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 5-12
Technical Paper | Reactor | doi.org/10.13182/NT78-A32085
Determination of the Net Free Containment Volume at the Trojan Nuclear Plant Using an Experimental-Analytical Technique
George R. Fegan, Daniel I. Herborn, Steven M. Lippincott
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 13-18
Technical Paper | Reactor | doi.org/10.13182/NT78-A32086
The Use of the Method of Characteristics for Examination of Two-Phase Flow Behavior
A. Tentner, J. Weisman
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 19-28
Technical Paper | Reactor | doi.org/10.13182/NT78-A32087
Tokamak Fusion Power Reactors
Weston M. Stacey, Jr., Mohamed A. Abdou
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 29-39
Technical Paper | Reactor | doi.org/10.13182/NT78-A32088
Dealing with Uncertainty in Fuel Rod Modeling
Sidney Oldberg, Jr., Ronald A. Christensen
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 40-47
Technical Paper | Fuel | doi.org/10.13182/NT78-A32089
Failed Fuel Pin Performance in Fast Metal-Cooled Reactors
H. Plitz
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 48-58
Technical Paper | Fuel | doi.org/10.13182/NT78-A32090
Catalytic Trapping of Methylradioiodide by Beds of Impregnated Charcoal
Victor R. Deitz, Leonard A. Jonas
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 59-64
Technical Paper | Radioisotope | doi.org/10.13182/NT78-A32091
Monte Carlo Analysis of the Effects of a Blanket-Shield Penetration on the Performance of a Tokamak Fusion Reactor
R. T. Santoro, J. S. Tang, R. G. Alsmiller, Jr., J. M. Barnes
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 65-72
Technical Paper | Shielding | doi.org/10.13182/NT78-A32092
Neutron Gauging to Detect Voids in Polyurethane
Francis Y. Tsang, Don M. Alger, Robert M. Brugger
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 73-78
Technical Paper | Instrument | doi.org/10.13182/NT78-A32093
Neutron Activation Analytical Determination of Small Amounts of Neptunium-237 in Solutions Containing Uranium, Plutonium, and Fission Products
Heinz Ruf, Margarete Friedrich
Nuclear Technology | Volume 37 | Number 1 | January 1978 | Pages 79-83
Technical Paper | Analysis | doi.org/10.13182/NT78-A32094
Oxygen Monitoring and Control in Boiling Water Reactor Plants
W. L. Pearl, W. R. Kassen, S. G. Sawochka
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 94-98
Technical Paper | Plant Water Chemistry / Reactor | doi.org/10.13182/NT78-A31975
The Control of Cobalt-58 Dissolution During Refueling Shutdowns of Pressurized Water Reactors Using a Hydrogen Peroxide Addition
J. W. Kormuth
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 99-102
Technical Paper | Plant Water Chemistry / Reactor | doi.org/10.13182/NT78-A31976
Update of Operations with Westinghouse Steam Generators
D. D. Malinowski, W. D. Fletcher
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 103-110
Technical Paper | Plant Water Chemistry / Reactor | doi.org/10.13182/NT78-A31977
Water Chemistry Characterizations of a Boiling Water Reactor
A. D. Miller
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 111-117
Technical Paper | Plant Water Chemistry / Reactor | doi.org/10.13182/NT78-A31978
Condensing Heat Transfer Following a Loss-of-Coolant Accident
W. J. Krotiuk, M. B. Rubin
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 118-128
Technical Paper | Plant Water Chemistry / Reactor | doi.org/10.13182/NT78-A31979
Waste Management Considerations for Fusion Power Reactors
T. E. Botts, J. R. Powell
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 129-137
Technical Paper | Plant Water Chemistry / Fuel Cycle | doi.org/10.13182/NT78-A31980
Impurity Interaction Analysis in Mesh-Packed Cold Traps
Michio Murase, Isao Sumida, Koichi Kotani, Hajime Yamamoto
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 138-147
Technical Paper | Plant Water Chemistry / Material | doi.org/10.13182/NT78-A31981
Criticality Studies for a Neutron Multiplier
R. C. Lloyd, S. R. Bierman, E. D. Clayton, B. M. Durst
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 148-158
Technical Paper | Plant Water Chemistry / Radioisotope | doi.org/10.13182/NT78-A31982
LEAD-210 from Nuclear Explosions in the Environment
Zbigniew Jaworowski, Ludwika Kownacka, Kazimierz Grotowski, Krzysztof Kwiatkowski
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 159-166
Technical Paper | Plant Water Chemistry / Nuclear Explosive | doi.org/10.13182/NT78-A31983
Autonomous System for Control of an Experiment with Scintillation and Čerenkov Counters
Dušan Kollár, Lubica Kollárová, Pavel Horváth
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 167-183
Technical Paper | Plant Water Chemistry / Instrument | doi.org/10.13182/NT78-A31984
Resource Utilization of Symbiotic High-Temperature Gas-Cooled Reactor Systems
G. M. Borgonovi, R. H. Brogli
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 196-203
Technical paper | Reactor | doi.org/10.13182/NT78-A31990
Effects of A Pipe Rupture Accident on the Reactor Internals in a Boiling Water Reactor Demonstrated by the Example of Philippsburg 1
Claus Elter, Eberhard Haug, Helmut Morassi
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 204-226
Technical paper | Reactor | doi.org/10.13182/NT78-A31991
Neutron Multiplication Factors as a Function of Temperature: A Comparison of Calculated and Measured Values for Lattices Using 233U02-Th02 Fuel in Graphite
Darrell F. Newman, Bryan F. Gore
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 227-245
Technical paper | Reactor | doi.org/10.13182/NT78-A31992
Boiling Water Reactor Scram Reactivity Characteristics
Hsiang-Shou Cheng, David J. Diamond, Ming-Shih Lu
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 246-260
Technical paper | Reactor | doi.org/10.13182/NT78-A31993
Core Exit Instrumentation of the Clinch River Breeder Reactor Plant
Mario D. Carelli
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 261-273
Technical paper | Reactor | doi.org/10.13182/NT78-A31994
NeutronIcs and Photonics Calculations for the Tokamak Experimental Power Reactor
R. T. Santoro, V. C. Baker, J. M. Barnes
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 274-295
Technical paper | Reactor | doi.org/10.13182/NT78-A31995
A Hierarchy Level Scheme for Quasi-Optimum Fuel Assembly Loading in Boiling Water Reactors
Koichi Sekimizu
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 296-312
Technical paper | Fuel Cycle | doi.org/10.13182/NT78-A31996
Quelques Caracteristiques De L’Air D’Une Mine D’Uranium
André Renoux, Jean Yves Barzic, Guy J. Madelaine, Pierre Zettwoog
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 313-327
Technical paper | Chemical Processing | doi.org/10.13182/NT78-A31997
A Radiological Assessment of Reprocessing Advanced Liquid-Metal Fast Breeder Reactor Fuels
J. E. Till, E. S. Bomar, L. E. Morse, V. J. Tennery
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 328-339
Technical paper | Fuel | doi.org/10.13182/NT78-A31998
Elimination of Transuranium Elements by Burnup in a Power Fast Breeder Reactor
G. Oliva, G. Palmiotti, M. Salvatores, L. Tondinelli
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 340-352
Technical paper | Fuel | doi.org/10.13182/NT78-A31999
Diffusion of Plutonium in High-Temperature Isotropic Pyrolytic Carbon
N. L. Baldwin, P. Winchell, S. Langer
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 353-357
Technical paper | Fuel | doi.org/10.13182/NT78-A32000
