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
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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
