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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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Power Burst Facility Fuel Studies
J. T. Cole, R. E. Wood
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 9-22
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31535
(U,Zr)C-Graphite Fuel for TREAT Converter Studies
Keith V. Davidson
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 23-30
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31536
Fuel Elements for Pulsed TRIGA® Research Reactors
Massoud T. Simnad, Fabian C. Foushee, Gordon B. West
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 31-56
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31537
Material Property Determination for Fast Pulsed Reactor Fuels by Rapid Fission Heating
J. A. Reuscher, T. R. Schmidt
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 57-67
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31538
A Measurement of Temperature-Dependent Internal Friction for Uranium, U—0.78 wt% Ti, U—6 wt% Mo, and U—10 wt% Mo
E. T. Laats, T. R. Schmidt, J. A. Reuscher
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 68-76
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31539
Fabrication of Uranium-Molybdenum Alloy Fuels for Pulsed Reactors
James M. Taub
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 77-86
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31540
Summary of Unpublished Presentations for Fuels for Pulsed Reactors
James A. Horak
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 87-91
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31541
Clinch River Breeder Reactor Breeding Characteristics
G. C. Tillett, Jr., A. R. Buhl
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 92-97
Technical Paper | Fuels for Pulsed Reactor / Reactor | doi.org/10.13182/NT76-A31542
Fusion-Fission Hybrid Concepts for Laser-Induced Fusion
James Maniscalco
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 98-107
Technical Paper | Fuels for Pulsed Reactor / Reactor | doi.org/10.13182/NT76-A31543
A Method for Generating a Control Rod Program for Boiling Water Reactors
Toshio Kawai, Hiroshi Motoda, Takashi Kiguchi, Michihiro Ozawa
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 108-118
Technical Paper | Fuels for Pulsed Reactor / Reactor | doi.org/10.13182/NT76-A31544
Hydrodynamic Containment for Underground Nuclear Power Plants
J. M. Cardito, E. V. Somers, J. H. McWhirter
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 119-126
Technical Paper | Fuels for Pulsed Reactor / Reactor Siting | doi.org/10.13182/NT76-A31545
Fission Gas Behavior in Oxide Fuel Elements of Fast Breeder Reactors
H. Zimmermann
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 127-133
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31546
Statistical and Metallurgical Analyses of Experimental Mark-IA Driver Fuel Element Cladding Failures in the Experimental Breeder Reactor II
N. J. Olson, C. M. Walter, W. N. Beck
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 134-151
Technical Paper | Fuels for Pulsed Reactor / Fule | doi.org/10.13182/NT76-A31547
Computational Experiments with a Californium-252 Source for Possible Use in Neutron Radiography
D. Kedem, M. Lemanska
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 152-158
Technical Paper | Fuels for Pulsed Reactor / Radioisotope | doi.org/10.13182/NT76-A31548
Some Studies of Reflector Construction and Electronics Configurations for Optimizing Pulse-Height and Pulse-Shape Resolution in Alpha Liquid-Scintillation Spectrometry
John W. McKlveen, W. J. McDowell
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 159-164
Technical Paper | Fuels for Pulsed Reactor / Instrument | doi.org/10.13182/NT76-A31549
An In-Line Station for Volume Calibration of Raschig-Ring-Filled Storage Tanks for Fissile Solution
Robert E. Rothe, Louis W. Doher, A. L. Johnston
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 165-171
Technical Note | Fuels for Pulsed Reactor / Chemical Processing | doi.org/10.13182/NT76-A31550
Laboratory Experiments to Check Cooling Tower Computer Models
Heinrich Werle
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Page 172
Technical Note | Fuels for Pulsed Reactor / Technique | doi.org/10.13182/NT76-A31551
Simulated and Simultaneous Loss-of-Coolant Accident Testing of Protective Coatings for the Nuclear Industry
W. F. Oberbeck, Jr., K. G. Mayhan, D. R. Edwards, J. R. Lopata, J. F. Montle, D. R. Leritz
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 183-193
Technical Paper | Reactor | doi.org/10.13182/NT76-A31558
The Probability of a Turbine Missile Hitting a Particular Region of a Nuclear Power Plant
A. K. Bhattacharyya, S. K. Chaudhuri
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 194-198
Technical Paper | Reactor | doi.org/10.13182/NT76-A31559
Hazards to Nuclear Plants from Off-Site Release of Toxic Vapors
Karl Hornyik
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 199-207
Technical Paper | Reactor Siting | doi.org/10.13182/NT76-A31560
Strategy, Design Basis, and Results of the Carbide Program for SNR
G. Karsten, G. Mühling, H. Plitz
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 208-215
Technical Paper | Fuel | doi.org/10.13182/NT76-A31561
Actinides and Fission Products Distribution in Fast Breeder Nitride Fuel
G. Giacchetti, C. Sari, C. T. Walker
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 216-225
Technical Paper | Fuel | doi.org/10.13182/NT76-A31562
Surface Diffusion of Plutonium on Uranium Dioxide
Hirotaka Furuya, Masumichi Koizumi
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 226-234
Technical Paper | Material | doi.org/10.13182/NT76-A31563
Metamictization of Lithium Niobate by Thermal Neutrons
William Primak, T. T. Anderson
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 235-248
Technical Paper | Material | doi.org/10.13182/NT76-A31564
Corrosion Behavior, Mechanical Properties, and Long-Term Aging of Nickel-Plated Uranium
J. W. Dini, H. R. Johnson, C. W. Schoenfelder
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 249-255
Technical Paper | Material | doi.org/10.13182/NT76-A31565
Thermal Diffusion of Oxygen in PuO2-y
C.Sari, G.Schumacher
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 256-260
Technical Paper | Material | doi.org/10.13182/NT76-A31566
Transmission of Gamma Radiation Through Finite Cylindrical Barriers
E. Elias, Y. Segal, A. Notea
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 261-269
Technical Paper | Radiation | doi.org/10.13182/NT76-A31567
A Proton Recoil Scintillation Technique for Estimating Neutron Energy Spectra
P. K. Sarkar, K. N. Kirthi, A. K. Ganguly
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 270-281
Technical Paper | Technique | doi.org/10.13182/NT76-A31568
Improved Nondestructive Determination of Two-Dimensional Radial Isotopic Distributions in Irradiated Fuel Pins
John R. Phillips
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 282-290
Technical Paper | Technique | doi.org/10.13182/NT76-A31569
Materials Development for Advanced Reactors
G. W. Cunningham
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 301-304
Technical Paper | Reactor | doi.org/10.13182/NT76-A31512
Design of the Clinch River Breeder Reactor Plant Steam Generators
J. C. Whipple, C. N. Spalaris
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 305-314
Technical Paper | Reactor | doi.org/10.13182/NT76-A31513
High-Temperature Gas-Cooled Reactor Steam Generator Design
W. G. Schuetzenduebel
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 315-327
Technical Paper | Reactor | doi.org/10.13182/NT76-A31514
Materials in Candu Steam Generators from the Designer's Point of View
S. Vandeth, R. L. Hemmings
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 328-338
Technical Paper | Reactor | doi.org/10.13182/NT76-A31515
Design and Manufacturing Experience for the German Thorium High-Temperature Reactor 300-MW(e) Steam Generator
Hans W. Fricker
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 339-347
Technical Paper | Reactor | doi.org/10.13182/NT76-A31516
Materials Performance in Operating Pressurized Water Reactor Steam Generators
John R. Weeks
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 348-355
Technical Paper | Reactor | doi.org/10.13182/NT76-A31517
Operating Experience with Westinghouse Steam Generators
W. D. Fletcher, D. D. Malinowski
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 356-373
Technical Paper | Reactor | doi.org/10.13182/NT76-A31518
Fabrication and Inspection Development for Clinch River Breeder Reactor Plant Steam Generators
R. W. McClung, G. M. Slaughter, C. N. Spalaris, A. F. Lillie
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 374-382
Technical Paper | Reactor | doi.org/10.13182/NT76-A31519
N Reactor Steam Generator Performance
P. A. Carlson, W. K. Kratzer
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 383-387
Technical Paper | Reactor | doi.org/10.13182/NT76-A31520
Caustic Stress Corrosion Cracking of Inconel-600, Incoloy-800, and Type 304 Stainless Steel
G. J. Theus
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 388-397
Technical Paper | Reactor | doi.org/10.13182/NT76-A31521
Clinch River Breeder Reactor Environmental Effects-General Water-Side Corrosion
J. H. DeVan, J. C. Griess
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 398-405
Technical Paper | Reactor | doi.org/10.13182/NT76-A31522
Effects of Service Environments on the Behavior of High-Temperature Gas-Cooled Reactor Steam Generator Structural Materials
F. N. Mazandarany, P. L. Rittenhouse
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 406-423
Technical Paper | Reactor | doi.org/10.13182/NT76-A31523
The Behavior of Metals in High-Temperature Reactor Helium for Steam Generators
H. G. A. Bates, W. Betteridge, R. H. Cook, L. W. Graham, D. F. Lupton
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 424-440
Technical Paper | Reactor | doi.org/10.13182/NT76-A31524
Compatibility of Fe-2¼ wt% Cr-1 wt% Mo Steel in a Sodium Environment
K. Natesan, O. K. Chopra, T. F. Kassner
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 441-451
Technical Paper | Reactor | doi.org/10.13182/NT76-A31525
Carbon Transfer Behavior of Materials for Liquid-Metal Fast Breeder Reactor Steam Generators
Keishi Matsumoto, Yoshio Ohta, Tadayuki Kataoka, Shigeji Yagi, Katsumi Suzuki, Teruo Yukitoshi, Taishi Moroishi, Kunihiko Yoshikawa, Yoshiaki Shida
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 452-470
Technical Paper | Reactor | doi.org/10.13182/NT76-A31526
The Effects of Ten Years Experimental Breeder Reactor II Service on 2¼ Cr-1 Mo Steel
J. A. Shields, Jr., K. J. Longua
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 471-481
Technical Paper | Reactor | doi.org/10.13182/NT76-A31527
French Steam Generator Experience-Phenix and Beyond
M. G. Robin
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 482-489
Technical Paper | Reactor | doi.org/10.13182/NT76-A31528
Mechanical and Physical Properties of 2¼ Cr-1 Mo Steel in Support of Clinch River Breeder Reactor Plant Steam Generator Design
C. R. Brinkman, R. K. Williams, R. L. Klueh, T. L. Hebble
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 490-505
Technical Paper | Reactor | doi.org/10.13182/NT76-A31529
Comparison of Various Chromium-Molybdenum Low-Alloy Steels for Liquid-Metal Fast Breeder Reactor Steam Generators
Teruo Yukitoshi, Taishi Moroishi, Isamu Koizumi, Takashi Abe, Kunihiko Yoshikawa, Yoshiaki Shida
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 506-515
Technical Paper | Reactor | doi.org/10.13182/NT76-A31530
U.S. Advanced Materials Development Program for Steam Generators
P. Patriarca, S. D. Harkness, J. M. Duke, L. R. Cooper
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 516-536
Technical Paper | Reactor | doi.org/10.13182/NT76-A31531
