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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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Identification of Nuclear Systems
T. W. Kerlin, G. C. Zwingelstein, B. R. Upadhyaya
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 7-38
Technical Paper | Critical Review | doi.org/10.13182/NT77-A31954
Radiation Qualification of Nuclear Reactor Components
J. A. Naber, N. A. Lurie
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 40-47
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31956
Normal Operating Radiation Levels in Pressurized Water Reactor Plants
J. Sejvar
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 48-55
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31957
Calculation of Accident Doses to Equipment Inside Containment of Powe Reactors
Michael J. Kolar, Nolan C. Olson
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 56-64
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31958
Consideration of the Effect of Iodine Plateout on Containment Post-Loss-of-Coolant Accident Doses
Eugene Normand
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 65-73
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31959
Post-Loss-of-Coolant Accident Doses to Pressurized Water Reactor Equipment
Michael J. Kolar, John R. McCarty, Nolan C. Olson
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 74-78
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31960
Stability of Lithium Niobate on Irradiation at Elevated Temperature
William Primak, A. P. Gavin, T. T. Anderson, Emmet Monahan
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 79-84
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31961
A Possible Mechanism for Corrosion Product Transport and Radiation Field Growth in a Pressurized Water Reactor Primary Circuit
K. A. Burrill
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 85-92
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31962
Nuclear Reactor Control System Design with Sensor Failure
L. F. Miller, R. G. Cochran, J. W. Howze
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 93-105
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31963
Conversion of Waste Zircaloy Hulls to Zirconate Ion Exchange Materials for Waste Stabilization
H. S. Levine, E. J. Nowak
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 106-119
Radiation Environments in Nuclear Reactor Power Plant | Chemical Processing | doi.org/10.13182/NT77-A31964
The Production of Molten UO2 Pools by Internal Heating: Apparatus and Preliminary Experimental Heat Transfer Results
M. G. Chasanov, W. H. Gunther, L. Baker, Jr.
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 120-128
Radiation Environments in Nuclear Reactor Power Plant | Fuel | doi.org/10.13182/NT77-A31965
On the Simulation of Fast Breeder Reactor Pin Behavior Using UO2 Pins with Direct Electrical Heating
A. Alexas
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 129-138
Radiation Environments in Nuclear Reactor Power Plant | Fuel | doi.org/10.13182/NT77-A31966
Calculation of the Fragmentation of UO2 by Capacitor Discharge: Nonequilibrium Model
R. G. Alsmiller, Jr., R. B. Perez, J. Barish
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 139-147
Technical Note | Material | doi.org/10.13182/NT77-A31967
Comparison of Measured and Calculated Nitrogen-16 Activity in Water for Application to Nuclear-Powered Ship Reactor Designs
J. B. Sun, H. D. Warren
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 249-261
Technical Paper | Reactor | doi.org/10.13182/NT77-A31939
Design Considerations for Large Heterogeneous Liquid-Metal Fast Breeder Reactors
Constantine P. Tzanos, W. P. Barthold
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 262-274
Technical Paper | Reactor | doi.org/10.13182/NT77-A31940
A Practical Means for Pressure Transducer Response Verification
David G. Cain, Carleton G. Foster
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 275-284
Technical Paper | Reactor | doi.org/10.13182/NT77-A31941
Energy Optimization of a Cycled Tokamak
Peter S. Martini, Ronald J. Onega
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 285-293
Technical Paper | Reactor | doi.org/10.13182/NT77-A31942
Feasibility Study of Core Management System by Data Communication for Boiling Water Reactors
Hiroshi Motoda, Satoshi Tanisaka, Takashi Kiguchi, Haruo Yonenaga
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 294-304
Technical Paper | Fuel Cycle | doi.org/10.13182/NT77-A31943
Computation Studies of Cladding Relocation Dynamics During Liquid-Metal Fast Breeder Reactor Transient Undercooling Accidents
G. Angerer
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 305-313
Technical Paper | Fuel | doi.org/10.13182/NT77-A31944
Solid Waste as Refuse-Derived Fuel
R. Fred Rolsten, Leon Glaspell, J. P. Waltz
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 314-327
Technical Paper | Economic | doi.org/10.13182/NT77-A31945
An Optimal Set of Selected Uranium Enrichments That Minimizes Blending Consequences
Joel A. Nachlas, Harold A. Kurstedt, Jr., John S. Lorber, Jr.
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 328-335
Technical Paper | Economic | doi.org/10.13182/NT77-A31946
Damage Function for the Mechanical Properties of Steels
A. Alberman, J. P. Genthon, L. Salon, G. Allegraud
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 336-346
Technical Paper | Material | doi.org/10.13182/NT77-A31947
Stress-Free Swelling in Type 304 Stainless Steel at High Fluences
T. A. Kenfield, W. K. Appleby, H. J. Busboom
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 347-352
Technical Paper | Material | doi.org/10.13182/NT77-A31948
The Creep-Rupture Properties of a Weld-Overlaid Type 304 Stainless-Steel Forging
R. L. Klueh, D. A. Canonico
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 353-367
Technical Paper | Material | doi.org/10.13182/NT77-A31949
Fission Rate Measurements with the Makrofol Solid-State Track Recorder
Dariush Azimi-Garakani, John Garnett Williams
Nuclear Technology | Volume 36 | Number 3 | December 1977 | Pages 368-378
Technical Paper | Technique | doi.org/10.13182/NT77-A31950
Preparing the Implementation of Non-Proliferation Treaty Safeguards in the U.S.
Wolfgang Frenzel, Vladimir Shmelev, Adolf Von Baeckmann
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 158-162
Technical Paper | International Safeguard / Fuel Cycle | doi.org/10.13182/NT77-A31921
Report on an International Atomic Energy Agency Inventory Verification
George H. Winslow, A. Lee Harkness
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 163-166
Technical Paper | International Safeguard / Fuel Cycle | doi.org/10.13182/NT77-A31922
The Use of Fuel Reprocessing Plant Instrumentation for International Safeguards
Arnold L. Ayers
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 167-170
Technical Paper | International Safeguard / Fuel Cycle | doi.org/10.13182/NT77-A31923
Impurity Radiation from Medium Density Plasmas
G. R. Hopkins, John M. Rawls
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 171-186
Technical Paper | International Safeguard / Reactor | doi.org/10.13182/NT77-A31924
Radiographic Control of Materials Testing Reactor Fuel on X-Ray Paper
J. C. Domanus
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 187-192
Technical Paper | International Safeguard / Reactor | doi.org/10.13182/NT77-A31925
A Neutron-Gamma Chemonuclear Fusion Reactor
VI-Duong Dang, Meyer Steinberg
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 193-199
Technical Paper | International Safeguard / Reactor | doi.org/10.13182/NT77-A31926
Intrusion of Molten Steel into Cracks in Solid Fuel in a Transient-Undercooling Accident in a Liquid-Metal Fast Breeder Reactor
R. W. Ostensen, W. F. Murphy, B. J. Wrona, L. W. Deitrich, J. C. Florek
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 200-214
Technical Paper | International Safeguard / Reactor | doi.org/10.13182/NT77-A31927
The Isolation of Radioiodine with Portland Cement. Part I: Scoping Leach Studies
Walter E. Clark
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 215-221
Technical Paper | International Safeguard / Chemical Processing | doi.org/10.13182/NT77-A31928
Differences in the 103Ru and 106Ru Axial Distributions in (U,Pu)O2 Fuel Pins
J. R. Phillips, T. K. Marshall
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 222-228
Technical Paper | International Safeguard / Fuel | doi.org/10.13182/NT77-A31929
Reactor Hydrodynamics During the Reflood Phase of a Loss-of-Coolant Accident
Rodney R. Gay
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 229-237
Technical Note | International Safeguard / Reactor | doi.org/10.13182/NT77-A31930
