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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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Boiling Water Reactor Control Rod Programming Using Heuristic and Mathematical Methods
Tamotsu Hayase, Hiroshi Motoda
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 91-100
Technical Paper | Reactor | doi.org/10.13182/NT80-A32455
A Radionuclide Trap for Liquid-Metal-Cooled Reactors
J. C. McGuire, W. F. Brehm
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 101-109
Technical Paper | Reactor | doi.org/10.13182/NT80-A32456
Reaction Rate Calculations in Uranium and Thorium Blankets Surrounding a Central Deuterium-Tritium Neutron Source
A. D. Krumbein, M. Lemanska, M. Segev, J. J. Wagschal, A. Yaari
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 110-116
Technical Paper | Reactor | doi.org/10.13182/NT80-A32457
Rotating Plug Size Study for Liquid-Metal Fast Breeder Reactors
L. J. Nemeth
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 117-121
Technical Paper | Reactor | doi.org/10.13182/NT80-A32458
Experimental Value of Percent Variation in Root-Mean-Square Ex-Core Detector Signal to the Core Barrel Amplitude Scale Factor
J. P. Thompson, G. R. McCoy, B. T. Lubin
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 122-127
Technical Paper | Reactor | doi.org/10.13182/NT80-A32459
Critical Experiments with Solid Neutron Absorbers and Water-Moderated Fast Test Reactor Fuel Pins
B. M. Durst, S. R. Bierman, E. D. Clayton, J. F. Mincey
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 128-149
Technical Paper | Fuel | doi.org/10.13182/NT80-A32460
Remodeling and Dosimetry on the Neutron Irradiation Facility of the Musashi Institute of Technology Reactor for Boron Neutron Capture Therapy
Otohiko Aizawa, Keiji Kanda, Tetsuya Nozaki, Tetsuo Matsumoto
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 150-163
Technical Paper | Radiation | doi.org/10.13182/NT80-A32461
Subcritical Limits for Special Fissile Actinides
H. K. Clark
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 164-170
Technical Paper | Analysis | doi.org/10.13182/NT80-A32462
Effects of Indoor Residence on Radiation Doses from Routine Releases of Radionuclides to the Atmosphere
D. C. Kocher
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 171-179
Technical Note | Radioisotope | doi.org/10.13182/NT80-A32463
An Experimental Technique for Determination of Steam Fraction in Flowing Steam / Air Mixtures
N. Saba, R. T. Lahey, Jr., J. C. Corelli
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 5-15
Technical Paper | Reactor | doi.org/10.13182/NT80-A32443
Pellet and Pellet-Blanket Neutronics and Photonics for Electron Beam Fusion
Magdi M. H. Ragheb, Gregory A. Moses, Charles W. Maynard
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 16-33
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32444
Multigoal Fuel Cycle Optimization Including Nonproliferation Objectives
P. Silvennoinen, T. Vieno, J. Vira
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 34-42
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32445
Fission Gas Release and Microscopic Swelling in Highly Rated Advanced Fuels
M. Coquerelle, C. T. Walker
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 43-53
Technical Paper | Fuel | doi.org/10.13182/NT80-A32446
Reprocessing Nuclear Fuels of the Future: A Radiological Assessment of Advanced (Th,U) Carbide Fuel
J. E. Till, H. R. Meyer, L. E. Morse, W. D. Bond, E. S. Bomar, V. J. Tennery
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 54-62
Technical Paper | Fuel | doi.org/10.13182/NT80-A32447
Analysis, Critique, and Reevaluation of High-Level Waste Repository Water Intrusion Scenario Studies
Bernard L. Cohen
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 63-69
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32448
Effects of Simulated Fission Products on the Mechanical Properties of Zircaloy-2
R. Kohli, F. Holub
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 70-76
Technical Paper | Material | doi.org/10.13182/NT80-A32449
Desorption Kinetics of Methyl Iodide from Impregnated Charcoal
Leonard A. Jonas, Victor R. Deitz, J. B. Romans
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 77-83
Technical Paper | Radioisotope | doi.org/10.13182/NT80-A32450
Dose Rates from Induced Activity in the Tokamak Fusion Test Reactor Test Cell
R. G. Alsmiller, Jr., J. Barish, R. T. Santoro, R. A. Lillie, J. M. Barnes, M. M. H. Ragheb
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 187-195
Technical Paper | Reactor | doi.org/10.13182/NT80-A32466
Impurity Deposition in a Mesh-Packed Cold Trap
Michio Murase, Isao Sumida, Norio Nagase, Kazuo Mukai, Osamu Onuki
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 196-203
Technical Paper | Reactor | doi.org/10.13182/NT80-A32467
Development Studies Regarding the Construction of Epithermal-Enriched Neutron Field for Medical Purposes at the University of Tokyo YAYOI Fast Reactor
Shigehiro An, Akira Furuhashi, Yoshiaki Oka, Masatsugu Akiyama, Hiroyuki Kuga,+, Harukuni Tanaka
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 204-215
Technical Paper | Reactor | doi.org/10.13182/NT80-A32468
Nuclear Performance of Molten Salt Fusion-Fission Symbiotic Systems for Catalyzed Deuterium-Deuterium and Deuterium-Tritium Reactors
M. M. H. Ragheb, R. T. Santoro, J. M. Barnes, M. J. Saltmarsh
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 216-232
Technical Paper | Reactor | doi.org/10.13182/NT80-A32469
On the Volatilization Potential of Metallic Inclusions Found in Irradiated UO2 Fuel During Overheating Events
Paul Sasa, August W. Cronenberg+, Michael G. Stevenson
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 233-250
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32470
Supercriticality Through Optimum Moderation in Nuclear Fuel Storage
J. M. Cano, R. Caro, J. M. Martnez-Val
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 251-260
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32471
International Symbiosis: The Role of Thorium and The Breeders
D. M. Ligon, R. H. Brogli
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 261-272
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32472
Development and Performance of Metal Fuel Elements for Fast Breeder Reactors
L. C. Walters, J. H. Kittel
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 273-280
Technical Paper | Fuel | doi.org/10.13182/NT80-A32473
The Effect of Low Pressurized Water Reactor Containment Pressure on Peak Cladding Temperatures
Vincent P. Manno
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 281-288
Technical Paper | Fuel | doi.org/10.13182/NT80-A32474
Application of Simplified Reliability Methods for Risk Assessment of Nuclear Waste Repositories
Andreas Pritzker, Jrg Gassmann
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 289-297
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32475
Corrosion of 15 Cr—35 Ni—50 Fe Doped with Niobium, Titanium, or Molybdenum in High Temperature Reactor Helium
Otto Demel
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 298-302
Technical Paper | Material | doi.org/10.13182/NT80-A32476
Empirical Development of Irradiation-Induced Swelling Design Equations
J. F. Bates, M. K. Korenko
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 303-314
Technical Paper | Material | doi.org/10.13182/NT80-A32477
