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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
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Damage Function Analysis of Austenitic-Steel Neutron-Induced Mechanical Property Change Data
R. L. Simons, W. N. McElroy, L. D. Blackburn
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 14-24
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31171
SCIM—A Theory Based Computer Code for the Prediction of the In-Pile Behavior of Type 304 Stainless Steel
S. D. Harkness, R. Grappel, S. G. McDonald
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 25-35
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31172
An Analysis of the Effects of Hydrostatic Stress on Swelling
J. L. Straalsund, G. L. Guthrie
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 36-44
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31173
Effect of Neutron Irradiation on the Ductility of Austenitic Stainless Steel
E. E. Bloom, J. R. Weir, Jr.
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 45-54
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31174
The Interrelationship Between Swelling and Irradiation Creep
W. G. Wolfer, J. P. Foster, F. A. Garner
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 55-63
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31175
An Evaluation of the Effect of Intergranular Attack on Fuel Pin Burst Properties
P. J. Ring, K. D. Challenger, H. J. Busboom
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 64-74
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31176
Performance of Mixed-Oxide Fuel Elements to 11 at.% Burnup
L. A. Neimark, J. D. B. Lambert, W. F. Murphy, C. W. Renfro
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 75-88
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31177
Fuel-Cladding Mechanical Interaction in LMFBR Fuel Rods
B. F. Rubin, T. J. Black, W. K. Appleby, J. D. Stephen, R. F. Hilbert
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 89-99
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31178
The Mechanical Design of TRISO-Coated Particle Fuels for the Large HTGR
T. D. Gulden, C. L. Smith, D. P. Harmon, W. W. Hudritsch
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 100-109
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31179
High Burnup Mixed-Oxide Fuel Irradiation Experiments
M. Coquerelle, J. Gabolde, R. Lesser, P. Werner
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 110-119
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31180
Porosity and Actinide Redistribution During Irradiation of (U, Pu)O2
W. J. Lackey, F. J. Homan, A. R. Olsen
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 120-142
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31181
Postirradiation Observations of Mixed Oxides with Initial Addition of Fission Product Elements
M. Conte, M. Mouchnino, F. K. Schmitz
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 143-155
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31182
The Development of CYGRO-F for Fuel Rod Behavior Analysis
B. L. Harbourne, M. S. Beck, J. P. Foster, A. Biancheria
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 156-170
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31183
Examination of F3A Series Unencapsulated Mixed-Oxide Fuel Pins Irradiated in EBR-II
W. H. McCarthy, K. J. Perry, G. R. Hull, J. W. Bennett
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 171-186
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31184
Boron Concentration Gradient for Improved Thermal Reactor Performance of Boron-Stainless-Steel Control Rods
R. J. Beaver, A. E. Richt
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 187-196
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31185
Irradiation-Induced Dimensional Change in Boronated Graphite
O. M. Stansfield
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 197-207
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31186
Empirical Helium Release Function from Thermal Reactor Irradiated Boron Carbide
G. E. Russcher, A. L. Pitner
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 208-215
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31187
Performance Modeling of Neutron Absorbers
F. J. Homan
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 216-225
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31188
Irradiation Behavior of Boron Carbide
G. L. Copeland, R. G. Donnelly, W. R. Martin
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 226-237
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31189
Irradiation Effects in Boron Carbide Pellets Irradiated in Fast Neutron Spectra
J. A. Basmajian, A. L. Pitner, D. E. Mahagin, H. C. F. Ripfel, D. E. Baker
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 238-248
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31190
The Structure of Sodium Corrosion Deposits and Their Effect on Heat Transfer Coefficients
W. E. Ray, R. L. Miller, S. L. Schrock, G. A. Whitlow
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 249-262
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31191
Sodium Corrosion and Mass Transfer Analysis with an Ion Probe Mass Spectrometer
E. Berkey, G. G. Sweeney, W. M. Hickam
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 263-277
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31192
Materials Creep Behavior and Elevated Temperature Design
L. D. Blackburn, J. C. Tobin, R. A. Moen
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 278-286
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31193
Creep Data Acquisition and Application to Reactor Component Design
D. J. Ayres, T. M. Cullen
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 287-296
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31194
Estimates of Creep-Fatigue Interaction in Irradiated and Unirradiated Austenitic Stainless Steels
C. R. Brinkman, G. E. Korth, R. R. Hobbins
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 297-307
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31195
Effect of Irradiation on the Strain Rate Dependence of Type 304 Stainless-Steel Mechanical Properties
J. M. Steichen
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 308-315
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31196
Fatigue-Crack Growth in 20% Cold-Worked Type 316 Stainless Steel at Elevated Temperatures
Lee A. James
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 316-322
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31197
Postirradiation Creep of Annealed Type 316 Stainless Steel
A. J. Lovell
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 323-331
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31198
Structural Materials Aspects of LMFBR Core Restraint System Design
W. E. Pennell
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 332-353
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31199
A Review of the Italian Activities for the Thermal Recycling of Plutonium
G. Schileo
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 360-366
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31202
Experimental Investigation of In-Reactor Molten Fuel Performance
C. Lepscky, G. M. Testa, H. Hougaard, K. W. Jones
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 367-395
Technical Paper | Fuel | doi.org/10.13182/NT72-A31203
Fluidized Bed Calcination of Radioactive Wastes Using In-Bed Combustion Heating
T. K. Thompson, G. E. Lohse, B. R. Wheeler
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 396-405
Technical Paper | Radioactive Waste | doi.org/10.13182/NT72-A31204
Dimensional Stability of Tantalum Control Rods in LMFBRs
J. F. Bates, A. L. Pitner
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 406-409
Technical Paper | Material | doi.org/10.13182/NT72-A31205
Fast Reactor Irradiation of Boron Carbide Powder
A. L. Pitner
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 410-417
Technical Paper | Material | doi.org/10.13182/NT72-A31206
A Mathematical Model for the Measurement of Gas Properties with Alpha-Particle Gauges
R. P. Gardner, K. Verghese, J. I. Cehn
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 418-429
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31207
Reduction of Tritium from Underground Nuclear Explosives
J. B. Green, Jr., R. M. Lessler
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 430-436
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT72-A31208
Ground Motion Prediction Method for Simultaneously Detonated Multiple Underground Nuclear Explosives
Dean V. Power
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 437-443
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT72-A31209
A Review of the Ground Motion Prediction Problem for Plowshare Underground Engineering Applications
Walter W. Hays
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 444-457
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT72-A31210
Measurement of Antiscatter Grid Effectiveness in Thermal-Neutron Radiography of Hydrogenous Materials
John A. Rau, William L. Parker
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 458-461
Technical Paper | Instrument | doi.org/10.13182/NT72-A31211
A Simplified Apparatus for Short-Term Irradiations at 77°K
P. R. Blankenhorn, D. E. Kline
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 462-464
Technical Note | Radioisotope | doi.org/10.13182/NT72-A31212
Distribution of Tritium in A Pressurized Water Power Reactor Plant
Pekka Jauho, Lasse Mattila
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 472-478
Technical Paper | Reactor | doi.org/10.13182/NT72-A31216
Analytical Investigation and Design of A Model Hydro-Dynamically Simulating A Prototype PWR Core
E. U. Khan
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 479-496
Technical Paper | Reactor | doi.org/10.13182/NT72-A31217
Analytical Studies of Elemental Iodine Removal by Sprays in the Donald C. Cook Nuclear Plant
S. J. Milioti, A. Sherman, R. L. Ritzman, J. A. Gieseke
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 497-508
Technical Paper | Reactor | doi.org/10.13182/NT72-A31218
Characterization of the Fracture Toughness of Zircaloy
T. J. Walker
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 509-520
Technical Paper | Material | doi.org/10.13182/NT72-A31219
Hold-Time Effects on the Elevated Temperature Fatigue-Crack Propagation of Type 304 Stainless Steel
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 521-530
Technical Paper | Material | doi.org/10.13182/NT72-A31220
Smoothed Values of the Enthalpy and Heat Capacity of UO2
Jerry F. Kerrisk, David G. Clifton
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 531-535
Technical Paper | Material | doi.org/10.13182/NT72-6
Annealing Behavior of Neutron-Irradiated Silicon Carbide Temperature Monitors
R. J. Price
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 536-542
Technical Paper | Material | doi.org/10.13182/NT72-A31222
Temperature in A Chimney Formed by an Underground Nuclear Experiment
D. E. Parks
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 543-555
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT72-A31223
Effects of Gamma Radiation on the Low-Temperature Dilute-Acid Hydrolysis of Cellulose
Nance D. Kunz, John L. Gainer, James L. Kelly
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 556-561
Technical Paper | Radiation | doi.org/10.13182/NT72-A31224
A Storage Container for Fissile Materials
C. L. Schuske, D. C. Hunt
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 562-565
Technical Note | Reactor | doi.org/10.13182/NT72-A31225
Silicon Oxynitride-A New Ceramic Material for Nuclear Applications
G. W. Keilholtz, R. E. Moore
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 566-567
Technical Note | Material | doi.org/10.13182/NT72-A31226
Development of Fission Gas Production Reactor Loop
Milton E. McLain, Jr.
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 568-569
Technical Note | Radioisotope | doi.org/10.13182/NT72-A31227