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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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Experiments of Anomaly Detection System of a Reactor Core
Y. Ohsawa, K. Kato, R. Oyamada
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 5-13
Technical Paper | Reactor | doi.org/10.13182/NT74-A31429
Anomalies of Criticality
E. D. Clayton
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 14-27
Technical Paper | Reactor | doi.org/10.13182/NT74-A31430
Evaluation of Air Traffic Hazards of Nuclear Plants
Karl Hornyik, John E. Grund
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 28-37
Technical Paper | Reactor Siting | doi.org/10.13182/NT74-A31431
State-of-the-Art in BWR Rod Bundle Burnout Predictions
D. Guarino, V. Marinelli, L. Pastori
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 38-52
Technical Paper | Fuel | doi.org/10.13182/NT74-A31432
The Effect of Carbide Precipitation on Fatigue Crack Propagation in Type 316 Stainless Steel
M. W. Mahoney, N. E. Paton
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 53-62
Technical Paper | Material | doi.org/10.13182/NT74-A31433
Interactions Between Stressed Zirconium Alloys and Iodine at 300°C
J. C. Wood
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 63-79
Technical Paper | Material | doi.org/10.13182/NT74-A31434
Comparison of Gamma Irradiation Performance of Three Neutron Fission Counters
L. D. Philipp, L. D. Muhlestein, M. R. Wood
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 80-86
Technical Paper | Instrument | doi.org/10.13182/NT74-A31435
Fast Neutron Flux Measurement Using Gas-Flow Techniques
D. P. Brown, W. G. Spear
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 87-93
Technical Paper | Instrument | doi.org/10.13182/NT74-A31436
Recent Developments in Nuclear Fuel Cycle Safeguards
William C. Bartels
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 101-105
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31441
Uranium Assay Requirements of Nuclear Accountability and Safeguards
Carleton D. Bingham, Morris W. Lerner
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 106-111
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31442
Design Concepts Study of a Special Nuclear Material Cargo Vehicle
R. E. Reed
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 112-116
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31443
A System for Communication with Commercial Special Nuclear Material Shipments
J. M. de Montmollin, T. A. Sellers
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 117-123
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31444
Portal Monitor for Diversion Safeguards
Thomas E. Sampson, Paul E. Fehlau, Gary M. Worth, Carl N. Henry
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 124-131
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31445
Chemical Assay of Plutonium for Safeguards
Darryl D. Jackson, James E. Rein, Glenn R. Waterbury
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 132-141
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31446
Security Seals for Safeguards
C. Sastre
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 142-145
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31447
Removal of Iodine by Sprays in the PSICO 10 Model Containment Vessel
S. Barsali, R. Bovalini, F. Fineschi, B. Guerrini, S. Lanza, M. Mazzini, R. Mirandola
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 146-156
Reactor | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT74-A31448
Surface Density Method Employing Unit Shape Factor (s/v) for the Storage of Fissile Materials
C. L. Schuske, D. Dickinson, S. J. Altschuler
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 157-176
Chemical Processing | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT74-A31449
Simplified Methods of Estimating the Results of Accidental Solution Excursions
Grover Tuck
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 177-188
Chemical Processing | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT23-177
A Quantitative Strain-and-Stress State Criterion for Failure in the Vicinity of Sharp Cracks
T. J. Walker
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Page 189
Material | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT74-A31451
Measurements of Neutron Fluxes in Strongly Absorbing Gaseous Media
W. Bixby, K. Almenas
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 213-221
Technical Paper | Reactor | doi.org/10.13182/NT74-A15914
Triangulation of Local Coolant Boiling by Cross-Correlating Acoustic Noise Signals
Hideaki Nishihara
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 222-232
Technical Paper | Reactor | doi.org/10.13182/NT74-A15915
A Methodology for Power Plant Site Selection at the Reconnaissance Level
Matthew C. Cordaro, William T. Malloy
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 233-239
Technical Paper | Reactor Siting | doi.org/10.13182/NT74-A15916
Plutonium Coated Particles Development
H. Bairiot, L. Aerts, E. Trauwaert, J. Vangeel
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 240-255
Technical Paper | Fuel | doi.org/10.13182/NT74-A15917
Triga Core Management Model
W. F. Naughton, M. J. Cenko, S. H. Levine, W. F. Witzig
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 256-272
Technical Paper | Fuel | doi.org/10.13182/NT74-A15918
Carbon Equilibrium Relationships for Austenitic Stainless Steels in a Sodium Environment
Stuart A. Shiels, Chris Bagnall, Steven L. Schrock
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 273-283
Technical Paper | Material | doi.org/10.13182/NT74-A15919
Flow Patterns in Sodium Cold Trap Crystallizer
David H. Lester, Gerald R. Bloom
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 284-289
Technical Paper | Material | doi.org/10.13182/NT74-A15920
The Influence of Gas Environments on Fatigue Crack Growth Rates in Types 316 and 321 Stainless Steel
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 290-297
Technical Paper | Material | doi.org/10.13182/NT74-A15921
Proton Dose Approximation in Arbitrary Convex Geometry
John W. Wilson, G. S. Khandelwal
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 298-305
Technical Paper | Shielding | doi.org/10.13182/NT74-A15922
Ray Tracing Through Reactor Shields
O. J. Wallace, N. D. Cook
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 306-317
Technical Paper | Shielding | doi.org/10.13182/NT74-A15923
A Continuous In-Line Monitor for UF6 Enrichment
T. D. Reilly, E. R. Martin, J. L. Parker, L. G. Speir, R. B. Walton
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 318-327
Technical Paper | Instrument | doi.org/10.13182/NT74-A15924
The Measurement of Extremely Low-Level Radioiodine in Air
N. P. Goldstein, K. H. Sun, J. L. Gonzalez
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 328-336
Technical Paper | Analysis | doi.org/10.13182/NT74-A15925
A Simple Device Using Capacitance Switches for Data Entry in Man-Machine Systems
Michael Danchak, William R. Moyer, Joseph R. Tatarczuk, Martin Becker
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 337-339
Technical Note | Instrument | doi.org/10.13182/NT74-A15926
