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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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Experimental Emergency Core Cooling Results from LOFT Non-Nuclear Tests
L. P. Leach, L. J. Ybarrondo, G. D. McPherson
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 126-149
Technical Paper | Reactor | doi.org/10.13182/NT77-A31772
The Interaction and Protection of Superconducting Poloidal Field Coils and Toroidal Field Coils in a Tokamak Experimental Power Reactor
H. T. Yeh, J. W. Lue
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 150-160
Technical Paper | Reactor | doi.org/10.13182/NT77-A31773
Bypass Flow Distribution in a Boiling Water Reactor
Roger W. Carlson, David R. Gott
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 161-173
Technical Paper | Reactor | doi.org/10.13182/NT77-A31774
Energy Investment in Nuclear and Solar Power Plants
G. Moraw, M. Schneeberger, A. Szeless
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 174-183
Technical Paper | Reactor | doi.org/10.13182/NT77-A31775
Plutonium Assemblies in Reload 1 of the Dodewaard Reactor
H. Bairiot, P. Deramaix, C. Vandenberg, L. Leenders, P. Mostert
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 184-202
Technical Paper | Reactor | doi.org/10.13182/NT77-A31776
The Human Cost of Regulatory Delays
Tobias W. T. Burnett
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 203-211
Technical Paper | Reactor Siting | doi.org/10.13182/NT77-A31777
Analysis of Electrical Power Generation Costs
R. W. Hardie, J. H. Chamberlin
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 212-222
Technical Paper | Economic | doi.org/10.13182/NT77-A31778
An Anomalous Reactivity Meter
H. A. Larson, J. I. Sackett
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 223-230
Technical Paper | Instrument | doi.org/10.13182/NT77-A31779
Thermographic Imaging of Nuclear Fuel Rods
Sidney Oldberg, Jr., Richard C. Honey, David G. Falconer, Edwin L. Zebroski
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 231-234
Technical Paper | Instrument | doi.org/10.13182/NT77-A31780
Minimum Critical Mass of Plutonium-Polyethylene System Found to Be Significantly Lower Than Plutonium-Water System
Jack K. Thompson
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 235-236
Technical Note | Chemical Processing | doi.org/10.13182/NT77-A31781
Combined Free and Forced Convection Effects on Transient Temperature Distributions in a Scaled-Down Model of the Inlet Plenum of the SNR-300 Reactor
J. F. L. M. Brukx, G. P. R. Hansen, P. Voj
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 5-16
Technical Paper | Reactor | doi.org/10.13182/NT77-A31759
Experimental Verification of a Method for Simulating a Boiling Water Reactor Core Based on a Few-Group Coarse-Mesh Diffusion Scheme
Sadao Uchikawa
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 17-29
Technical Paper | Reactor | doi.org/10.13182/NT77-A31760
Plutonium Release from Burning Sodium
J. L. Stakebake, H. N. Robinson
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 30-39
Technical Paper | Reactor | doi.org/10.13182/NT77-A31761
Experimental Investigation of Fuel-Coolant Interaction
Wiktor Śyszkowski
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 40-59
Technical Paper | Fuel | doi.org/10.13182/NT77-A31762
Analysis of the Venting System of the Gas-Cooled Fast Breeder Reactor Fuel Element for Various Operating Conditions
Klaus W. Klein
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 60-67
Technical Paper | Fuel | doi.org/10.13182/NT77-A31763
Preparation and Characterization of Sintered Glass-Ceramics from Calcined Simulated High-Level Waste
E. G. Samsel, J. R. Berreth
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 68-75
Technical Paper | Radioactive Waste | doi.org/10.13182/NT77-A31764
Mechanical Properties of Liquid-Metal Fast Breeder Reactor Primary Piping Materials
Charles R. Brinkman, Vinod K. Sikka, Roy T. King
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 76-95
Technical Paper | Material | doi.org/10.13182/NT77-A31765
Modification of the Existing Yielding Creep Theory of Irradiation Creep in Zirconium and Zircaloy-2
P. K. Madden, R. V. Hesketh
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 96-102
Technical Paper | Material | doi.org/10.13182/NT77-A31766
Neutron Flux Measurement at the LAMPF Radiation Effects Facility
Dennis G. Perry, Margaret L. Simmons, James S. Gilmore
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 103-109
Technical Paper | Accelerator | doi.org/10.13182/NT77-A31767
Comment on the Interpretation and Application of Limiting Critical Concentrations of Fissile Nuclides in Water
E. D. Clayton, B. M. Durst
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 110-111
Technical Note | Chemical Processing | doi.org/10.13182/NT77-A31768
The Effect of Chemistry Variations on the Short-Term Rupture Life and Tensile Properties of 20% Cold-Worked Type 316 Stainless Steel
D. R. Duncan, M. M. Paxton
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 112-119
Technical Note | Material | doi.org/10.13182/NT77-A31769
Reactor Containment Heat Removal by Passive Heat Sinks Following a Loss-of-Coolant Accident
P. S. Ayyaswamy, J. N. Chung, K. K. Niyogi
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 243-247
Technical Paper | Reactor | doi.org/10.13182/NT77-A31785
A Study of Post-Accident Molten Fuel Downward Streaming Through the Axial Shield Structure in the Liquid-Metal Fast Breeder Reactor
Ronald D. Gasser, Mujid S. Kazimi
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 248-259
Technical Paper | Reactor | doi.org/10.13182/NT77-A31786
Removal of Iodine from Reactor Fuel Solutions as Insoluble Pdl2
J. C. Mailen, D. E. Horner
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 260-263
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31787
Nuclear Heating in a Control Element of a Gas-Cooled Fast Breeder Reactor
A. Razani, S. Yee, M. Nagel
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 264-274
Technical Paper | Fuel | doi.org/10.13182/NT77-A31788
Nonequilibrium Evaporation and Condensation in Liquid-Metal Fast Breeder Reactor Fuel Expansion
J. G. Refling, A. B. Reynolds, P. L. Garner, S. P. Rao
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 275-289
Technical Paper | Fuel | doi.org/10.13182/NT77-A31789
The Determination of Defective Particle Fraction in High-Temperature Gas-Cooled Reactor Fuels
D. E. LaValle, D. A. Costanzo, W. J. Lackey, A. J. Caputo
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 290-295
Technical Paper | Fuel | doi.org/10.13182/NT77-A31790
New Methods for Measuring Neutron Spectra with Energy from 0.4 eV to 10 MeV by Track and Activation Detectors
J. J. Doroshenko, S. N. Kraitor, T. V. Kuznetsova, K. K. Kushnereva, E. S. Leonov
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 296-304
Technical Paper | Instrument | doi.org/10.13182/NT77-A31791
Dual Gauging Utilizing Penetrating and Scattered Photon Fluxes
E. Elias, Y. Segal, A. Notea
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 305-313
Technical Paper | Instrument | doi.org/10.13182/NT77-A31792
Pressure Drop of Spacer Grids in Smooth and Roughened Rod Bundles
K. Rehme
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 314-317
Technical Note | Fuel | doi.org/10.13182/NT77-A31793
The Spatial Variation of the Damage Energy and Gas Production in the Experimental Volume of a Li(D,n) Neutron Radiation Damage Facility
R. G. Alsmiller, Jr., J. Barish
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 318-321
Technical Note | Material | doi.org/10.13182/NT77-A31794
