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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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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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Power-Distribution Control by Absorber Deficit Compensation
Herbert Finnemann, Helmut Moldaschl
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 7-11
Technical Paper | Reactor | doi.org/10.13182/NT76-A31694
Load-Follow Demonstrations Employing Constant Axial Offset Power-Distribution Control Procedures
P. J. Sipush, R. A. Kerr, A. P. Ginsberg, T. Morita, L. R. Scherpereel
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 12-31
Technical Paper | Reactor | doi.org/10.13182/NT76-A31695
A Comparison of the Deuterium-Tritium Neutron Wall Load Distributions in Several Tokamak Fusion Reactor Designs
David L. Chapin, William G. Price, Jr.
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 32-47
Technical Paper | Reactor | doi.org/10.13182/NT76-A31696
Evaluation of Subcooled Water Thrust Forces
Stephen W. Webb
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 48-52
Technical Paper | Reactor | doi.org/10.13182/NT76-A31697
Economic Alternatives for the Long-Term Use of Plutonium Produced in Light Water Reactors
K. Hnilica, H. P. Holley, K. Lahner, H. Schmale
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 53-61
Technical Paper | Fuel Cycle | doi.org/10.13182/NT76-A31698
Behavior of Molybdenum in Mixed-Oxide Fuel
G. Giacchetti, C. Sari
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 62-69
Technical Paper | Fuel | doi.org/10.13182/NT76-A31699
Caustic Stress-Corrosion Behavior of Fe-Ni-Cr Nuclear Steam Generator Tubing Alloys
I. L. W. Wilson, F. W. Pement, R. G. Aspden, R. T. Begley
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 70-84
Technical Paper | Material | doi.org/10.13182/NT76-A31700
Notch Effect on the Tensile Properties of Fast-Reactor-Irradiated Type 304 Stainless Steel
Robert L. Fish
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 85-95
Technical Paper | Material | doi.org/10.13182/NT76-A31701
Residual Cold Work and Its Influence on Tensile and Creep Properties of Types 304 and 316 Stainless Steel
V. K. Sikka, R. W. Swindeman, T. L. Hebble, C. R. Brinkman, M. K. Booker
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 96-114
Technical Paper | Material | doi.org/10.13182/NT76-A31702
Temperature and Fluence Limits for a Type 316 Stainless-Steel Controlled Thermonuclear Reactor First Wall
E. E. Bloom, F. W. Wiffen, P. J. Maziasz, J. O. Stiegler
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 115-122
Technical Paper | Material | doi.org/10.13182/NT76-A31703
Detection of Sodium Boiling in Liquid-Metal Fast Breeder Reactors by Monitoring Neutron Noise Signals for Oscillatory Components
Joachim Ehrhardt
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 123-132
Technical Paper | Instrument | doi.org/10.13182/NT76-A31704
Prediction of Time-Dependent Neutron Fluxes Encountered in Pulsed-Neutron Uranium Logging Experiments
James H. Renken
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 133-139
Technical Paper | Radiation | doi.org/10.13182/NT76-A31705
Some Effects of Preinjected Helium and Irradiation Temperature in Void Formation in Aluminum Irradiated with Aluminum Ions
M. L. Sundquist, J. M. Donhowe
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 140-143
Technical Note | Material | doi.org/10.13182/NT76-A31706
Maximum Neutron Wall Loadings in Beam-Driven Tokamak Reactors
D. L. Jassby, H. H. Towner
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 159-163
Technical Paper | Reactor | doi.org/10.13182/NT76-A31678
Research on a 2700-MW(th) Pebble-Bed Reactor for a Helium-Turbine Power Plant
H. Jochem Rütten, Eberhard Teuchert
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 164-171
Technical Paper | Reactor | doi.org/10.13182/NT76-A31679
Tritium Diffusion in Fusion Reactor Blankets
J. M. Mintz, T. S. Elleman, K. Verghese
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 172-182
Technical Paper | Reactor | doi.org/10.13182/NT76-A31680
Fabrication, Properties, and Irradiation Behavior of U/Pu Particle Fuel for Light Water Reactors
Helfrid W. H. Lahr
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 183-190
Technical Paper | Fuel | doi.org/10.13182/NT76-A31681
Crushing Strength of High-Temperature Gas-Cooled Reactor Fuel Particles
W. J. Lackey, D. P. Stinton, L. E. Davis, R. L. Beatty
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 191-201
Technical Paper | Fuel | doi.org/10.13182/NT76-A31682
Incentives for Partitioning High-Level Waste
H. C. Burkholder, M. O. Cloninger, D. A. Baker, G. Jansen
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 202-217
Technical Paper | Radioactive Waste | doi.org/10.13182/NT76-A31683
Hydrogen and Oxygen Behavior in Liquid Sodium (Experimental)
Hiroji Katsuta, Kazuo Furukawa
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 218-231
Technical Paper | Material | doi.org/10.13182/NT76-A31684
Effect of Neutron Irradiation on the Microstructure and Properties of Titanium-Stabilized Type 316 Stainless Steels
E. E. Bloom, J. M. Leitnaker, J. O. Stiegler
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 232-243
Technical Paper | Material | doi.org/10.13182/NT76-A31685
Shielding Calculation Techniques for the Design of Plutonium Processing Facilities
T. C. Gillett, R. S. Denning, J. L. Ridihalgh
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 244-249
Technical Paper | Shielding | doi.org/10.13182/NT76-A31686
Neutron Radiography of Fast Transient Processes
G. S. Okawara, A. A. Harms
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 250-256
Technical Paper | Instrument | doi.org/10.13182/NT76-A31687
Reactor Flux Measurements Using Thermoluminescent Dosimetry
John W. McKlveen, Michael Schwenk
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 257-263
Technical Paper | Technique | doi.org/10.13182/NT76-A31688
Design and Performance of a Microwave Strain Measuring System for Materials Tests
T. Roger Billeter, L. D. Blackburn
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 264-275
Technical Paper | Technique | doi.org/10.13182/NT76-A31689
Observations on the Luminescence of α-AI2O3 (Synthetic Sapphire) in a Reactor Environment
R. N. Davie, Jr., J. F. Davis III, R. T. Schneider
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 276-278
Technical Note | Material | doi.org/10.13182/NT76-A31690
Direct Measurement of Cesium Adsorption on High-Temperature Surfaces Using Radioactive Tracers
R. K. Collier, C. E. Backus
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 279-281
Technical Note | Technique | doi.org/10.13182/NT76-A31691
Experimental Study on Fast-Neutron Streaming Through a Grid-Plate Shield of a Liquid-Metal Fast Breeder Reactor
Yoshiaki Oka, Hiroaki Wakabayashi, Shigehiro An, Ikunori Suzuki
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 287-296
Technical Paper | Reactor | doi.org/10.13182/NT76-A31665
Molten Fuel-Coolant Interaction During Hypothetical Accidents in Light Water Reactors
Victor Teschendorff, Adly Barsoum Wahba
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 297-305
Technical Paper | Reactor | doi.org/10.13182/NT76-A31666
Fast Reactor Transfer Functions with Special Reference to the Nonlinearities and the Spatial Dependence of the Heat Transfer Process
L. Caldarola, P. Ferranti, F. Mitzel
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 306-318
Technical Paper | Reactor | doi.org/10.13182/NT76-A31667
Recent State Laws Regulating Power Facility Siting
Victoria A. Evans
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 319-325
Technical Paper | Reactor Siting | doi.org/10.13182/NT76-A31668
Civil Defense Implications of the U.S. Nuclear Power Industry During a Large Nuclear War in the Year 2000
Conrad V. Chester, Rowena O. Chester
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 326-338
Technical Paper | Reactor Siting | doi.org/10.13182/NT76-A31669
Reactivity Measurements Under Conditions Typical to Fuel Element Dissolution
S. R. Bierman
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 339-347
Technical Paper | Chemical Processing | doi.org/10.13182/NT76-A31670
The Effect of Variable Thermal Conductivity in Thermal-Hydraulic Calculations
David A. Rehbein, Roger W. Carlson
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 348-356
Technical Paper | Fuel | doi.org/10.13182/NT76-A31671
Effect of Pellet Cracking on Light Water Reactor Fuel Temperatures
P. E. MacDonald, J. Weisman
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 357-366
Technical Paper | Fuel | doi.org/10.13182/NT76-A31672
Alloy 800 for Liquid-Metal Fast Breeder Reactor Steam Generators
M. Julien
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 367-374
Technical Paper | Material | doi.org/10.13182/NT76-A31673
Updated Measure of Radiation Damage Exposure
K. Shure
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 375-384
Technical Paper | Material | doi.org/10.13182/NT76-A31674
