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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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Experiments of Anomaly Detection System of a Reactor Core
Y. Ohsawa, K. Kato, R. Oyamada
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 5-13
Technical Paper | Reactor | doi.org/10.13182/NT74-A31429
Anomalies of Criticality
E. D. Clayton
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 14-27
Technical Paper | Reactor | doi.org/10.13182/NT74-A31430
Evaluation of Air Traffic Hazards of Nuclear Plants
Karl Hornyik, John E. Grund
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 28-37
Technical Paper | Reactor Siting | doi.org/10.13182/NT74-A31431
State-of-the-Art in BWR Rod Bundle Burnout Predictions
D. Guarino, V. Marinelli, L. Pastori
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 38-52
Technical Paper | Fuel | doi.org/10.13182/NT74-A31432
The Effect of Carbide Precipitation on Fatigue Crack Propagation in Type 316 Stainless Steel
M. W. Mahoney, N. E. Paton
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 53-62
Technical Paper | Material | doi.org/10.13182/NT74-A31433
Interactions Between Stressed Zirconium Alloys and Iodine at 300°C
J. C. Wood
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 63-79
Technical Paper | Material | doi.org/10.13182/NT74-A31434
Comparison of Gamma Irradiation Performance of Three Neutron Fission Counters
L. D. Philipp, L. D. Muhlestein, M. R. Wood
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 80-86
Technical Paper | Instrument | doi.org/10.13182/NT74-A31435
Fast Neutron Flux Measurement Using Gas-Flow Techniques
D. P. Brown, W. G. Spear
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 87-93
Technical Paper | Instrument | doi.org/10.13182/NT74-A31436
Recent Developments in Nuclear Fuel Cycle Safeguards
William C. Bartels
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 101-105
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31441
Uranium Assay Requirements of Nuclear Accountability and Safeguards
Carleton D. Bingham, Morris W. Lerner
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 106-111
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31442
Design Concepts Study of a Special Nuclear Material Cargo Vehicle
R. E. Reed
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 112-116
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31443
A System for Communication with Commercial Special Nuclear Material Shipments
J. M. de Montmollin, T. A. Sellers
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 117-123
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31444
Portal Monitor for Diversion Safeguards
Thomas E. Sampson, Paul E. Fehlau, Gary M. Worth, Carl N. Henry
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 124-131
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31445
Chemical Assay of Plutonium for Safeguards
Darryl D. Jackson, James E. Rein, Glenn R. Waterbury
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 132-141
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31446
Security Seals for Safeguards
C. Sastre
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 142-145
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31447
Removal of Iodine by Sprays in the PSICO 10 Model Containment Vessel
S. Barsali, R. Bovalini, F. Fineschi, B. Guerrini, S. Lanza, M. Mazzini, R. Mirandola
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 146-156
Reactor | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT74-A31448
Surface Density Method Employing Unit Shape Factor (s/v) for the Storage of Fissile Materials
C. L. Schuske, D. Dickinson, S. J. Altschuler
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 157-176
Chemical Processing | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT74-A31449
Simplified Methods of Estimating the Results of Accidental Solution Excursions
Grover Tuck
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 177-188
Chemical Processing | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT23-177
A Quantitative Strain-and-Stress State Criterion for Failure in the Vicinity of Sharp Cracks
T. J. Walker
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Page 189
Material | Nuclear Safeguards (Presented at November 1973 Meeting) | doi.org/10.13182/NT74-A31451
Measurements of Neutron Fluxes in Strongly Absorbing Gaseous Media
W. Bixby, K. Almenas
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 213-221
Technical Paper | Reactor | doi.org/10.13182/NT74-A15914
Triangulation of Local Coolant Boiling by Cross-Correlating Acoustic Noise Signals
Hideaki Nishihara
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 222-232
Technical Paper | Reactor | doi.org/10.13182/NT74-A15915
A Methodology for Power Plant Site Selection at the Reconnaissance Level
Matthew C. Cordaro, William T. Malloy
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 233-239
Technical Paper | Reactor Siting | doi.org/10.13182/NT74-A15916
Plutonium Coated Particles Development
H. Bairiot, L. Aerts, E. Trauwaert, J. Vangeel
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 240-255
Technical Paper | Fuel | doi.org/10.13182/NT74-A15917
Triga Core Management Model
W. F. Naughton, M. J. Cenko, S. H. Levine, W. F. Witzig
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 256-272
Technical Paper | Fuel | doi.org/10.13182/NT74-A15918
Carbon Equilibrium Relationships for Austenitic Stainless Steels in a Sodium Environment
Stuart A. Shiels, Chris Bagnall, Steven L. Schrock
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 273-283
Technical Paper | Material | doi.org/10.13182/NT74-A15919
Flow Patterns in Sodium Cold Trap Crystallizer
David H. Lester, Gerald R. Bloom
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 284-289
Technical Paper | Material | doi.org/10.13182/NT74-A15920
The Influence of Gas Environments on Fatigue Crack Growth Rates in Types 316 and 321 Stainless Steel
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 290-297
Technical Paper | Material | doi.org/10.13182/NT74-A15921
Proton Dose Approximation in Arbitrary Convex Geometry
John W. Wilson, G. S. Khandelwal
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 298-305
Technical Paper | Shielding | doi.org/10.13182/NT74-A15922
Ray Tracing Through Reactor Shields
O. J. Wallace, N. D. Cook
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 306-317
Technical Paper | Shielding | doi.org/10.13182/NT74-A15923
A Continuous In-Line Monitor for UF6 Enrichment
T. D. Reilly, E. R. Martin, J. L. Parker, L. G. Speir, R. B. Walton
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 318-327
Technical Paper | Instrument | doi.org/10.13182/NT74-A15924
The Measurement of Extremely Low-Level Radioiodine in Air
N. P. Goldstein, K. H. Sun, J. L. Gonzalez
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 328-336
Technical Paper | Analysis | doi.org/10.13182/NT74-A15925
A Simple Device Using Capacitance Switches for Data Entry in Man-Machine Systems
Michael Danchak, William R. Moyer, Joseph R. Tatarczuk, Martin Becker
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 337-339
Technical Note | Instrument | doi.org/10.13182/NT74-A15926
