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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Jump to:
Materials Considerations in Radioactive Waste Storage
Warren K. Eister
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 6-9
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31731
Hanford Waste Encapsulation: Strontium and Cesium
R. R. Jackson
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 10-15
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31732
Stabilization and Storage of Solidified High-Level Radioactive Wastes
J. R. Berreth, A. P. Hoskins, J. A. Rindfleisch
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 16-24
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31733
Packaging Rocky Flats Waste
Charles E. Wickland
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 25-29
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31734
Some Techniques for the Solidification of Radioactive Wastes in Concrete
Peter Colombo, Robert M. Neilson, Jr.
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 30-38
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31735
Leach Behavior of Hydrofracture Grout Incorporating Radioactive Wastes
J. G. Moore, H. W. Godbee, A. H. Kibbey
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 39-52
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31736
Packaging of Tritium-Contaminated Liquid Waste
E. A. Mershad, W. W. Thomasson, J. J. Dauby
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 53-59
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31737
The Canadian Spent Fuel Storage Canister: Some Materials Aspects
Derek G. Boase, Tjalle T. Vandergraaf
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 60-71
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31738
High-Level Waste Glass
John E. Mendel
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 72-87
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31739
High-Level Waste Glass: Field Leach Test
W. F. Merritt
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 88-91
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31740
High-Level Waste Ceramics: Materials Considerations, Process Simulation, and Product Characterization
Gregory J. McCarthy
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 92-105
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31741
In Situ Regeneration of Fusion Reactor First Walls
J. Chin, T. Ohkawa
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 115-124
Technical Paper | Reactor | doi.org/10.13182/NT77-A31717
Analysis of Reactor Component Fluence Limits Using Damage Function Methods
G. R. Odette, R. L. Simons, W. N. McElroy, D. G. Doran
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 125-141
Technical Paper | Reactor | doi.org/10.13182/NT77-A31718
Toroidal Field Strength Requirements in Tokamak Reactors
W. M. Stacey, Jr., K. Evans, Jr.
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 142-154
Technical Paper | Reactor | doi.org/10.13182/NT77-A31719
Sensitivity Assessments in Reactor Safety Analysis
J. E. Kelly, F. L. Leverenz, Jr., N. J. McCormick, R. C. Erdmann
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 155-166
Technical Paper | Reactor | doi.org/10.13182/NT77-A31720
Study of the Dissolution of Refractory PuO2 in Nitric-Hydrofluoric Acid Dissolvents at 100°C
O. K. Tallent, J. C. Mailen
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 167-175
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31721
Uranium-236 in Light Water Reactor Spent Fuel Recycled to an Enriching Plant
A. de la Garza
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 176-185
Technical Paper | Fuel | doi.org/10.13182/NT77-A31722
The Reactivity Perturbation Assay of Irradiated Fuel Rods
L. Green, J. T. Kriese, M. Natelson
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 186-204
Technical Paper | Fuel | doi.org/10.13182/NT77-A31723
A Gamma-Ray Perimeter Security System
Donald A. Close
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 205-210
Technical Paper | Radioisotope | doi.org/10.13182/NT77-A31724
Optimal Synthesis of a Power Plant Cooling System
L. T. Fan, David F. Aldis
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 222-238
Technical Paper | Reactor | doi.org/10.13182/NT77-A31747
Properties of Light Water Reactor Core Melts
S. Nazaré, G. Ondracek, B. Schulz
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 239-246
Technical Paper | Reactor | doi.org/10.13182/NT77-A31748
Reliability Analysis of the Decay Heat Removal System of a 1000-MW(e) Gas-Cooled Fast Breeder Reactor
D. Bittermann, J. Wehling
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 247-256
Technical Paper | Reactor | doi.org/10.13182/NT77-A31749
Comparison of the Power Distribution in Uranium and Plutonium Fuel Elements in the KWO Core
Dieter Sommer
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 257-275
Technical Paper | Reactor | doi.org/10.13182/NT77-A31750
Mechanical Response of UO2 Subjected to Transient Heating
B. J. Wrona, J. T. A. Roberts, T. M. Galvin, G. T. Higgins
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 276-289
Technical Paper | Fuel | doi.org/10.13182/NT77-A31751
The Overall Probability of Detection in Connection with the Optimization of Safeguards Effort
Günter Hartmann
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 290-296
Technical Paper | Material | doi.org/10.13182/NT77-A31752
Equilibrium Pressure and Solubility of Hydrogen in Liquid Lithium
Hiroji Katsuta, Takahiro Ishigai, Kazuo Furukawa
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 297-303
Technical Paper | Material | doi.org/10.13182/NT77-A31753
Sodium Purification by Cold Trapping at the Experimental Breeder Reactor II
J. T. Holmes, C. R. F. Smith, M. M. Osterhout, W. H. Olson
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 304-314
Technical Paper | Material | doi.org/10.13182/NT77-A31754
A Californium-252 Fission Spectrum Irradiation Facility for Neutron Reaction Rate Measurements
J. A. Grundl, V. Spiegel, C. M. Eisenhauer, H. T. Heaton II, D. M. Gilliam, J. Bigelow
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 315-319
Technical Paper | Radioisotope | doi.org/10.13182/NT77-A31755
The Application of SPOOL-FIRE in Theoretical Analysis and Experimental Comparison
Lucy Wu Person
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 320-325
Technical Note | Reactor | doi.org/10.13182/NT77-A31756