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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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An Improved Objective Function for FBR’s Optimization Studies
P. Goldschmidt
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 6-14
Technical Paper | Fuel | doi.org/10.13182/NT73-A31249
Pressure Drop Correlations for Fuel Element Spacers
Klaus Rehme
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 15-23
Technical Paper | Fuel | doi.org/10.13182/NT73-A31250
Postirradiation Mechanical Properties of Types 304 and 304 +0.15% Titanium Stainless Steel
E. E. Bloom, J. O. Stiegler
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 24-37
Technical Paper | Material | doi.org/10.13182/NT73-A31251
Collection of Particulate Matter from Smokestacks Using Gamma-Ray Ionization
M. A. Schultz, M. E. Crotzer, W. R. Knapick
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 38-48
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A31252
On-Line Radiochemical Analysis for Controlling Rapid Ion Exchange Recovery of Transplutonium Elements
M. A. Wakat, S. F. Peterson
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 49-57
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A31253
Socioeconomic Aspects of a Plowshare Project
Harry J. Otway, Leo van der Harst, Gary H. Higgins
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 58-65
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT73-A31254
Measurement of Total Attenuation Coefficients for 6- to 10-MeV Photons
K. U. Ahmed, R. G. Cochran
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 66-70
Technical Paper | Radiation | doi.org/10.13182/NT73-A31255
Estimation of Errors Caused by Radiation and Temperature on Coaxial Signal Cables
J. L. Stringer, R. R. Bourassa, G. J. Dau
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 71-78
Technical Paper | Technique | doi.org/10.13182/NT73-A31256
Variability of Dose Reduction Factor as Applied to Reactor Containment Spray Systems
Thomas L. Hebble
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 79-81
Technical Note | Reactor | doi.org/10.13182/NT73-A31257
Separation of Molybdenum from Plutonium-238 Dioxide
W. A. Zanotelli, G. L. Silver, W. C. Bowling, S. B. Wells
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 82-84
Technical Note | Chemical Processing | doi.org/10.13182/NT73-A31258
Fast Reactor Fuel Interactions with Floor Material After a Hypothetical Core Meltdown
G. Jansen, D. D. Stepnewski
Nuclear Technology | Volume 17 | Number 1 | January 1973 | Pages 85-95
Technical Note | Fuel | doi.org/10.13182/NT73-A31259
Production and Release of Positron Emitters from Water-Moderated Power Reactors
Mike Sohan Singh, Lawrence Ruby
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 104-109
Technical Paper | Reactor | doi.org/10.13182/NT73-A31237
A Model for the Safe Storage of Fissile Solutions
S. J. Altschuler, C. L. Schuske
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 110-126
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A31238
Compatibility of Strontium Compounds with Superalloys at 900 and 1100°C
J. R. DiStefano
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 127-142
Technical Paper | Material | doi.org/10.13182/NT73-A31239
Post-Accident Hydrogen Generation from Protective Coatings in Power Reactors
H. E. Zittel
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 143-146
Technical Paper | Material | doi.org/10.13182/NT73-A31240
Linear Thermal Expansion of Plutonium Dioxide
M. Tokar, A. W. Nutt, T. K. Keenan
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 147-152
Technical Paper | Material | doi.org/10.13182/NT73-A31241
Effect of Long-Time Exposure to Liquid Sodium on a Welded AISI Type 304 Stainless-Steel Pipe
G. A. Ratz
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 153-159
Technical Paper | Material | doi.org/10.13182/NT73-A31242
Performance Experience with Prototype Betacel Nuclear Batteries
M. Lewis, S. E. Seeman
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 160-167
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A31243
Stochastic Fluctuation in a Uranium-Enriching Cascade Using the Centrifuge Process
Takashi Kiguchi, Hiroshi Motoda, Toshio Kawai
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 168-183
Technical Paper | Isotopes Separation | doi.org/10.13182/NT73-A31244
Determination by Neutron Radiography of the Location of Polymeric Resins Injected in Rock Fissures
R. V. Subramanian, David Burkhart
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 184-188
Technical Paper | Instrument | doi.org/10.13182/NT73-A31245
A High Resolution Thermal-Neutron Radiography Facility
D. M. Alger, S. R. Bull
Nuclear Technology | Volume 17 | Number 2 | February 1973 | Pages 189-192
Technical Paper | Instrument | doi.org/10.13182/NT73-A31246
Breakdown Pulse Noise in Insulated Systems for LMFBR Application
R. R. Schemmel, L. D. Philipp, J. L. Stringer
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 198-204
Technical Paper | Reactor | doi.org/10.13182/NT73-A31263
EBRFLOW—A Computer Program for Predicting the Coolant Flow Distribution in the Experimental Breeder Reactor-II
A. Gopalakrishnan, J. L. Gillette
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 205-216
Technical Paper | Reactor | doi.org/10.13182/NT73-A31264
Neutron Shielding Problems in the Shipping of High Burnup Thermal Reactor Fuel
H. S. Bailey, R. N. Evatt, G. L. Gyorey, C. P. Ruiz
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 217-224
Technical Paper | Fuel | doi.org/10.13182/NT73-A31265
Thermal Conductivity of Two-Phase Solid Bodies
J. P. Stora
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 225-233
Technical Paper | Material | doi.org/10.13182/NT73-A31266
Fast-Neutron Damage to Polycrystalline Alumina at Temperatures from 60 to 1230°C
G. W. Keilholtz, R. E. Moore, H. E. Robertson
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 234-246
Technical Paper | Material | doi.org/10.13182/NT73-A31267
Cyclic Activation with a Californium-252 Source
S. J. Gage, G. D. Atkinson, Jr., G. D. Bouchey
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 247-260
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A31268
Demonstration of Cobalt-60 Heat Source Capsule Performance
C. L. Angerman
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 261-274
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A31269
Radioactivity Monitor for Power Plant Environmental Water
G. Riel, W. M. Hawkins, Jr., G. H. Liebler, D. Duffey
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 275-279
Technical Paper | Instrument | doi.org/10.13182/NT73-A31270
The Half-Life of Dysprosium-165
A. Haccoun, K. Preiss, G. Shani
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 280-281
Technical Note | Analysis | doi.org/10.13182/NT73-A31271
