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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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Irradiation Behavior of Experimental Mark-II Experimental Breeder Reactor II Driver Fuel
G. L. Hofman
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 7-22
Technical Paper | Reactor | doi.org/10.13182/NT80-A32408
Effect of Intrasubassembly Incoherencies on the Fast Test Reactor Unprotected Transient Overpower Accident
Shu-Chien Yung, Norman P. Wilburn
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 23-38
Technical Paper | Reactor | doi.org/10.13182/NT80-A32409
Analysis of the Differences in Breeding Ratio and Fissile Inventory Between Heterogeneous and Homogeneous Liquid-Metal Fast Breeder Reactors
Constantine P. Tzanos
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 39-50
Technical Paper | Reactor | doi.org/10.13182/NT80-A32410
Criticality Experiments with Subcritical Clusters of Low Enriched UO2 Rods in Water with Uranium or Lead Reflecting Walls
S. R. Bierman, B. M. Durst, E. D. Clayton
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 51-58
Technical Paper | Reactor | doi.org/10.13182/NT80-A32411
Development of a Dynamics Model for the Research Reactor Maria
Jerzy Kubowski
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 59-69
Technical Paper | Reactor | doi.org/10.13182/NT80-A32412
Gravitational Collision Efficiency of Post Hypothetical Core Disruptive Accident Liquid-Metal Fast Breeder Reactor Aerosols: Spherical Particles
G. A. Pertmer, S. K. Loyalka
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 70-90
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32413
The Role of Fission Gas and Fuel Melting in Fuel Response During Simulated Hypothetical Loss-of-Flow Transients
G. Bandyopadhyay, J. A. Buzzell
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 91-109
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32414
Design Against Weathering of Iodine Filters
Yakov Ben-Haim
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 110-118
Technical Paper | Chemical Processing | doi.org/10.13182/NT80-A32415
Helium Fill Gas Absorption in Pressurized UO2 Fuel Rods During Irradiation
K. Vinjamuri, D. E. Owen
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 119-124
Technical Paper | Fuel | doi.org/10.13182/NT80-A32416
Heat Transfer in Pressurized Water Reactor Components Most Often Subject to Thermal Shock
F. Parras, M. Bosser, D. Milan, G. Berthollon
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 125-152
Technical Paper | Fuel | doi.org/10.13182/NT80-A32417
Design of High-Performance Fuel Pin Simulators for Thermodynamic Experiments with Nuclear Fuel Elements
Valentin Casal
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 153-162
Technical Paper | Fuel | doi.org/10.13182/NT80-A32418
Ocean Dumping of High-Level Waste—An Acceptable Solution We Can “Guarantee”
Bernard Cohen
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 163-172
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32419
Laboratory Simulation of High-Level Liquid Waste Evaporation and Storage
Philip A. Anderson
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 173-180
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32420
Effects of Temperature Changes on the Swelling Behavior of 20% Cold-Worked AISI Type 316 Stainless Steel
J. P. Foster, A. Boltax
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 181-188
Technical Paper | Material | doi.org/10.13182/NT80-A32421
Analysis of 60Co Gamma-Ray Transport Through Air by Discrete-Ordinates Transport Codes
Nobuo Sasamoto, Kiyoshi Takeuchi
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 189-199
Technical Paper | Shielding | doi.org/10.13182/NT80-A32422
Radiation Transport in Earth for Neutron and Gamma-Ray Point Sources Above an Air-Ground Interface
R. A. Lillie, R. T. Santoro
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 200-207
Technical Paper | Shielding | doi.org/10.13182/NT80-A32423
Determination of the Concentration of Solutes in Liquids by Means of the (n,α) and (n,γ) Reactions
G. U. Greger, K. Schügerl
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 208-212
Technical Paper | Analysis | doi.org/10.13182/NT80-A32424
Accidental Criticality of a Fusion-Fission Hybrid Blanket Design
V. C. Badham, W. E. Kastenberg, G. C. Pomraning, D. Okrent
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 221-233
Technical Paper | Reactor | doi.org/10.13182/NT80-A32428
Deterministic Criteria Versus Probabilistic Analyses: Examining the Single Failure and Separation Criteria
W. W. Weaver
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 234-243
Technical Paper | Reactor | doi.org/10.13182/NT80-A32429
PLENUM-2A, A Program for Transient Analysis of Liquid-Metal Fast Breeder Reactor Outlet Plenums
Juan J. Carbajo, Paul A. Howard
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 244-265
Technical Paper | Reactor | doi.org/10.13182/NT80-A32430
Ultrasonic Inspection of Liquid-Metal Fast Breeder Reactor Steam Generator Duplex Tubing
K. J. Longua, G. K. Whitham, C. C. Allen
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 257-267
Technical Paper | Reactor | doi.org/10.13182/NT80-A32431
Heat Transfer of a Spray Droplet in a Nuclear Reactor Containment
Mitsugu Tanaka
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 268-281
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32432
Containment Response to Postulated Core Meltdown Accidents in the Fast Flux Test Facility
R. D. Gasser, W. T. Pratt
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 282-307
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32433
Evaporative Removal of Sodium from Reactor Components
F. H. Welch, O. P. Steele III
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 308-311
Technical Paper | Fuel | doi.org/10.13182/NT80-A32434
Radionuclide Transport Through Heterogeneous Media
Jörg Hadermann
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 312-323
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32435
Reduction in the Toxicity of Fission Product Wastes Through Transmutation with Deuterium-Tritium Fusion Neutrons
T. A. Parish, J. W. Davidson
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 324-342
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32436
An Improved Evaluation Model for Zircaloy Oxidation
Howard Ocken
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 343-357
Technical Paper | Material | doi.org/10.13182/NT80-A32437
Gas Generation by Self-Radiolysis of Tritiated Waste Materials
W. E. Tadlock, G. C. Abell, R. H. Steinmeyer
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 358-362
Technical Paper | Material | doi.org/10.13182/NT80-A32438
Nondestructive Fissile Isotopic Measurement Technique for Uranium-233–Uranium-235 Fuels Using Prompt and Delayed Fission Neutron Counting
E. J. Allen, S. R. McNeany
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 363-377
Technical Paper | Analysis | doi.org/10.13182/NT80-A32439
An Investigation of Particulate Corrosion Product Transients in the Primary Coolant of the Winfrith Steam Generating Heavy Water Reactor
F. A. Means, R. S. Rodliffe, K. Harding
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 385-396
Technical Paper | Reactor | doi.org/10.13182/NT80-A32392
Tritium and Fissile Fuel Exchange Between Hybrids, Fission Power Reactors, and Tritium Production Reactors
M. Z. Youssef, R. W. Conn, W. F. Vogelsang
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 397-405
Technical Paper | Reactor | doi.org/10.13182/NT80-A32393
Neutron Moderation in Inertial Confinement Fusion Pellets and Effects on Damage and Radioactive Inventory
F. Beranek, R. W. Conn
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 406-411
Technical Paper | Reactor | doi.org/10.13182/NT80-A32394
Shielding Calculations for the Tokamak Fusion Test Reactor Neutral Beam Injectors
R. T. Santoro, R. A. Lillie, R. G. Alsmiller, Jr, J. M. Barnes
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 412-420
Technical Paper | Reactor | doi.org/10.13182/NT80-A32395
Optimum Fuel Loading and Operation Planning for Light Water Reactor Power Stations. Part II: Boiling Water Reactor Case Study
Tsutomu Hoshino
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 421-435
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32396
Optimum Fuel Loading and Operation Planning for Light Water Reactor Power Stations. Part III: Incremental Cost Study
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 436-443
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32397
Plutonium Fuel Cycles in the Spectral Shift Controlled Reactor
F. M. Sider, R. A. Matzie
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 444-450
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32398
Confinement of Ruthenium Oxides Volatilized During Nuclear Fuels Reprocessing
Edward T. Maas, Jr., John M. Longo
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 451-456
Technical Paper | Chemical Processing | doi.org/10.13182/NT80-A32399
Uncertainty Analysis and Thermal Stored Energy Calculations in Nuclear Fuel Rods
Mitchel E. Cunningham, Courtney R. Hann, Anthony R. Olsen
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 457-467
Technical Paper | Fuel | doi.org/10.13182/NT80-A32400
Adsorption of Iodine Species with Ion Exchange Resins in Aqueous Solutions
Chien-Chang Lin, J. J. Younger
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 468-476
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32401
The Oxidation Kinetics of Some Zirconium Alloys in Flowing Carbon Dioxide at High Temperatures
Rajiv Kohli
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 477-484
Technical Paper | Material | doi.org/10.13182/NT80-A32402
Measurement of the Gamma Dose Rate Distribution in a Spent Fuel Assembly with a Thermoluminescent Detector
Akio Ohno, Shojiro Matsuura
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 485-493
Technical Paper | Hot Laboratory | doi.org/10.13182/NT80-A32403
Boundary Conditions for the Geospheric Transport Equation
Auguste Zurkinden
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 494-495
Technical Note | Radioactive Waste | doi.org/10.13182/NT80-A32404
The Effects of Fe-Ni-Co-V Structural Alloys on Fusion Reactor Neutronic Performance
J. M. Barnes, B. L. Bishop, R. T. Santoro, T. A. Gabriel
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 496-498
Technical Note | Material | doi.org/10.13182/NT80-A32405
