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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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The Unavailability of Systems Under Periodic Test and Maintenance
G. Apostolakis, T. L. Chu
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 5-15
Technical Paper | Reactor | doi.org/10.13182/NT80-A17065
Gas Tag Identification of Failed Reactor Assemblies—IV. Analysis Methods
J. A. Figg, N. J. McCormick, R. E. Schenter, F. Schmittroth
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 16-24
Technical Paper | Fuel | doi.org/10.13182/NT80-3
Irradiation Performance of Metallic Driver Fuel in Experimental Breeder Reactor II to High Burnup
Robert E. Einziger, Bobby R. Seidel
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 25-39
Technical Paper | Fuel | doi.org/10.13182/NT80-A17067
Turbulent Flow Split Model and Supporting Experiments for Wire-Wrapped Core Assemblies
Chong Chiu, Neil E. Todreas, Warren M. Rohsenow
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 40-52
Technical Paper | Fuel | doi.org/10.13182/NT80-A17068
Emanation Thermal Analysis—Results from Characterizing Intermediate Steps and Intermediate Products for Urania Spheres
Vladimír Balek, Miroslav Vobořil, Václav Baran
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 53-59
Technical Paper | Fuel | doi.org/10.13182/NT80-A17069
A Comparative Study of Tritium Breeding Performance of Lithium, Li2O, and Li7Pb2 Blankets in a Tokamak Power Reactor
Jungchung Jung
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 60-82
Technical Paper | Fuel | doi.org/10.13182/NT80-A17070
Suivi de Rupture de Gaine du Combustible Caramel: Experience CARINE
J. Gilbert, R. Marfaing, H. Vidal
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 83-87
Technical Paper | Fuel | doi.org/10.13182/NT80-A17071
The Effect of the Spontaneous Fission of Plutonium-240 on the Energy Release in a Nuclear Explosive
Sümer Şahin, Jacques Ligou
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 88-94
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT80-A17072
Use of Fuel Thermocouple Transient Response for Data Verification and Fuel Rod Modeling
Donald D. Lanning, Bruce O. Barnes, W. A. Scheffler
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 95-107
Technical Paper | Technique | doi.org/10.13182/NT80-A17073
Fueling Moving Ring Field-Reversed Mirror Reactor Plasmas
F. S. Felber
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 119-123
Technical Paper | Reactor | doi.org/10.13182/NT80-A32537
An Application of Information Divergence to Nuclear Reactor Noise Analysis
J. Nagashima, D. G. Andrews
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 124-135
Technical Paper | Reactor | doi.org/10.13182/NT80-A32538
Inherent Safety in the Design of Future Nuclear Plants
Edward Lantz
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 136-147
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32539
Dissolution and Storage Experiment with 4.75-wt%-235U-Enriched UO2 Rods
J. C. Manaranche, D. Mangin, L. Maubert, G. Colomb, G. Poullot
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 148-157
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32540
Characterization of Organics in Leachates from Low-Level Radioactive Waste Disposal Sites
A. J. Francis, C. R. Iden, B. J. Nine, C. K. Chang
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 158-163
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32541
Numerical Calculations of the Effect of Recombination on Sink Strengths in the Rate Theory of Void Swelling, Irradiation Creep, and Growth
R. Bullough, M. H. Wood
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 164-168
Technical Paper | Material | doi.org/10.13182/NT80-A32542
Effect of Gamma Radiation on the Release of Corrosion Products from Carbon Steel and Stainless Steel in High Temperature Water
Kenkichi Ishigure, Norihiko Fujita, Takaaki Tamura, Keichi Oshima
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 169-177
Technical Paper | Material | doi.org/10.13182/NT80-A32543
Uranium Isotope Enrichment by Chemical Method
Maomi Seko, Tetsuya Miyake, Kohji Inada, Kunihiko Takeda
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 178-186
Technical Paper | Isotopes Separation | doi.org/10.13182/NT80-A32544
An Appraisal of the Effect of Graphite Interlayers on the Tolerance of Water Reactor Fuel Rods to Power Ramp Defects
E. Smith
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 187-189
Technical Note | Fuel | doi.org/10.13182/NT80-A32545
The Effect of Accidental Steam Entry on Gas-Cooled Fast Reactor Integral Neutronics Parameters
S. K. Bhattacharyya, J. A. Morman, R. G. Bucher, D. M. Smith, W. R. Robinson, E. F. Bennett
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 197-218
Technical Paper | Reactor | doi.org/10.13182/NT80-A32524
Parametric Study of Radioactive Release from a Breached Containment
A. Kenigsberg, D. Hasan, E. Elias
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 219-224
Technical Paper | Reactor | doi.org/10.13182/NT80-A32525
TREAT Test E8 Simulating a Liquid-Metal Fast Breeder Reactor $3/s Overpower Accident with Irradiated Fast Test Reactor Type Fuel
Richard Simms, Robert K. LO, William F. Murphy, Alan B. Rothman, George S. Stanford
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 225-241
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32526
An Evaluation of the Plutonium Denaturing Concept as an Effective Safeguards Method
Carolyn D. Heising-Goodman
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 242-251
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32527
Using Fuel Performance to Determine Operating Limit Uncertainty Allowance
John F. Carew, David J. Diamond
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 252-256
Technical Paper | Fuel | doi.org/10.13182/NT80-A32528
An Evaluation of Fuel Motion in Recent TREAT Experiments with Liquid-Metal Fast Breeder Reactor Fuel
Richard Simms
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 257-266
Technical Paper | Fuel | doi.org/10.13182/NT80-A32529
To the Corrosion of Austenitic Steel in Sodium Loops
M. Schad
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 267-288
Technical Paper | Material | doi.org/10.13182/NT80-A32530
Application of a Sodium Austenitic Corrosion Model to a Fuel Rod
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 289-297
Technical Paper | Material | doi.org/10.13182/NT80-A32531
One-Dimensional Penetration of Molten UO2 into Substrate Limestone Concrete
R. Farhadieh, W. H. Gunther
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 298-306
Technical Paper | Material | doi.org/10.13182/NT80-A32532
A Thermal Neutron Coincidence Counting System
B. H. Erkkila, R. S. Marshall
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 307-313
Technical Paper | Instrument | doi.org/10.13182/NT80-A32533
