ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
Jump to:
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