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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Axial Distribution of Void Fraction in Subcooled Boiling
László Maróti
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 8-17
Technical Paper | Reactor | doi.org/10.13182/NT77-A31825
Statistical Utility Theory for Comparison of Nuclear Versus Fossil Power Plant Alternatives
S. Garribba, A. Ovi
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 18-37
Technical Paper | Reactor | doi.org/10.13182/NT77-A31826
Institutional and Environmental Aspects of Geothermal Energy Development
Ora R. Citron
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 38-42
Technical Paper | Reactor Siting | doi.org/10.13182/NT77-A31827
Empirical Investigations of the Diffusion of Waste Air Plumes in the Atmosphere
Kurt-Jürgen Vogt
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 43-57
Technical Paper | Reactor Siting | doi.org/10.13182/NT77-A31828
Some Aspects of the Thorium Fuel Cycle in Heavy-Water-Moderated Pressure Tube Reactors
S. Banerjee, S. R. Hatcher, A. D. Lane, H. Tamm, J. I. Veeder
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 58-68
Technical Paper | Fuel Cycle | doi.org/10.13182/NT77-A31829
High-Pressure Capsule for the Irradiation of Fuel Swelling Specimens in the FR2 Reactor
Heinz E. Haefner
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 69-74
Technical Paper | Fuel | doi.org/10.13182/NT77-A31830
Results of the Postirradiation Examinations of the Rapsodie-I Experiment Fuel Pins
D. Haas, J. Van de Velde, M. Gaube, J. Ketels, C. Van Loon
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 75-88
Technical Paper | Fuel | doi.org/10.13182/NT77-A31831
In-Line Monitoring of Effluents from High-Temperature Gas-Cooled Reactor Fuel Particle Preparation Processes by Mass Spectrometry
D. A. Lee, D. A. Constanzo, D. P. Stinton, J. A. Carpenter, Jr., W. T. Rainey, Jr., D. C. Canada, J. A. Carter
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 89-97
Technical Paper | Fuel | doi.org/10.13182/NT77-A31832
Influence of the Radial Temperature Gradient on Cladding Dilatation
H. Venker, M. Bober, G. Schumacher
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 98-100
Technical Paper | Fuel | doi.org/10.13182/NT77-A31833
Fatigue Crack Propagation in Types 304 and 308 Stainless Steel at Elevated Temperatures
D. T. Raske, C. F. Cheng
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 101-110
Technical Paper | Material | doi.org/10.13182/NT77-A31834
A Reusable Frame Greenhouse That Saves Money and Erection Time and Reduces Waste Generation
W. O. Greenhalgh, D. T. Ott
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 111-113
Technical Paper | Radioisotope | doi.org/10.13182/NT77-A31835
14.7-MeV Neutron Capture Cross-Section Measurements with Improved Activation Technique
G. Magnusson, I. Bergqvist
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 114-121
Technical Paper | Technique | doi.org/10.13182/NT77-A31836
Critical Heat Flux: A Review of Recent Publications
V. Marinelli
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 135-171
Technical Paper | Critical Review | doi.org/10.13182/NT77-A39695
Generator of Reactivity Functions
Jose Porto
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 172-178
doi.org/10.13182/NT77-A38428
José Porto
Technical Paper | Reactor | doi.org/10.13182/NT77-A39696
Recent Developments in the Design of Conceptual Fusion Reactors
F. L. Ribe
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 179-208
Technical Paper | Reactor | doi.org/10.13182/NT77-A39697
A Best-Judgment Analysis of Emergency Core Cooling System Performance
Timothy C. Kessler, Gary B. Fader
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 209-216
Technical Paper | Reactor | doi.org/10.13182/NT77-A39698
First Wall Thermal-Mechanical Analyses of the Reference Theta-Pinch Reactor
R. A. Krakowski, R. L. Hagenson, G. E. Cort
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 217-241
Technical Paper | Reactor | doi.org/10.13182/NT77-A39699
Reactivity Enhancement in Transportation and Storage Arrays Due to Fissile Material Density Reductions
B. L. Koponen
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 242-248
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A39700
CANDU Fuel-Power Ramp Performance Criteria
W. J. PENN, R. K. LO, J. C. WOOD
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 249-268
doi.org/10.13182/NT77-A38430
CANDU Fuel—Power Ramp Performance Criteria
W. J. Penn, R. K. Lo, J. C. Wood
Technical Paper | Fuel | doi.org/10.13182/NT77-A39701
Investigation of High-Temperature Reactor Heat Exchanger Materials
T. Serpekian, R. Hecker
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 269-289
Technical Paper | Material | doi.org/10.13182/NT77-A39702
Corrosion and Creep of Pressurized Stainless-Steel Tubes in Liquid Sodium at 873 and 973 K
Hans U. Borgstedt, Günther Frees, Helga Schneider
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 290-298
Technical Paper | Material | doi.org/10.13182/NT77-A39703
Transition Matrix Approach to the Solution of the Bateman Equations
George R. Fegan
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 299-305
Technical Paper | Radioisotope | doi.org/10.13182/NT77-A39704
An Improved Method for Operating Sodium System Cold Traps
Leo E. Chulos
Nuclear Technology | Volume 34 | Number 2 | July 1977 | Pages 306-307
Technical Note | Reactor | doi.org/10.13182/NT77-A39705
Nuclear Design Sensitivity Analysis for a Fusion Reactor
E. L. Simmons, Donald J. Dudziak, S. A. W. Gerstl
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 317-340
Technical Paper | Reactor | doi.org/10.13182/NT77-A31797
Application of the Bayes Equation to Predicting Reactor System Reliability
R. R. Fullwood, R. C. Erdmann, E. T. Rumble, G. S. Lellouche
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 341-346
Technical Paper | Reactor | doi.org/10.13182/NT77-A31798
Management Analysis of Nuclear Allocation for the Generation of Electricity
Petros T. Antonopoulos, Joe C. Turnage
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 347-361
Technical Paper | Reactor | doi.org/10.13182/NT77-A31799
Neutronics Studies of the Gas-Carried Lithium Oxide Cooling-Breeding Fusion Reactor Blanket and Shield
E. T. Cheng, T. Y. Sung, D. K. Sze
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 362-368
Technical Paper | Reactor | doi.org/10.13182/NT77-A31800
Elimination of Flow-Rate Fluctuations in the Core of the FRJ-2 Research Reactor and Its Usefulness for Reactor Operation
Johannes Wolters, Manfred Nickel
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 369-375
Technical Paper | Reactor | doi.org/10.13182/NT77-A31801
Uncertainties in Calculated Heating and Radiation Damage in the Toroidal Field Coil of a Tokamak Experimental Power Reactor Due to Neutron Cross-Section Errors
R. G. Alsmiller, Jr., J. Barish, C. R. Weisbin
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 376-386
Technical Paper | Reactor | doi.org/10.13182/NT77-A31802
The Cost Effectiveness of Remote Nuclear Reactor Siting
Friedrich Niehaus, Harry J. Otway
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 387-397
Technical Paper | Reactor Siting | doi.org/10.13182/NT77-A31803
Core-State Models for Fuel Management of Equilibrium and Transition Cycles in Pressurized Water Reactors
José M. Aragonés, José M. Martínezval, María R. Corella
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 398-411
Technical Paper | Fuel Cycle | doi.org/10.13182/NT77-A31804
Radiolytic Instability of Ferrous Sulfamate in Nuclear Process Solutions
Ned E. Bibler
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 412-415
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31805
Effects of Metal lon Impurities on PuO2 Dissolution in Nitric-Hydrofluoric Acid Solution
O. K. Tallent, J. C. Mailen
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 416-419
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31806
Solvent Performance in THTR Nuclear Fuel Reprocessing. Part I: Calculation of Doses Received by TBP-n-Paraffin Extractant in Reprocessing THTR Fuels Applying a THOREX Flowsheet
B.-G. Brodda, D. Heinen
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 420-427
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31807
Solvent Performance in THTR Nuclear Fuel Reprocessing. Part II: On the Formation of Dibutyl Phosphoric Acid by Radiolytic and Hydrolytic Degradation of the TBP-n-Paraffin Extractant
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 428-437
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31808
Fuel Failures in the Dodewaard Boiling Water Reactor
D. Cordall, R. M. Cornell, K. W. Jones, J. S. Waddington
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 438-448
Technical Paper | Fuel | doi.org/10.13182/NT77-A31809
La Vitrification en France des Solutions de Produits de Fission
Roger Bonniaud
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 449-460
Technical Paper | Radioactive Waste | doi.org/10.13182/NT77-A31810
