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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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ANS Student Conference 2025
April 3–5, 2025
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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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RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
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Visual In-Pile Fuel Disruption Experiments
G. L. Cano, R. W. Ostensen, M. F. Young
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 9-18
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32501
Study of Progressive Damage to Reinforced Concrete Structures Submitted to Dynamic Reversed Load
A. M. Sokolovsky, M. Livolant, J. Gauvain, A. Hoffmann
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 19-26
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32502
The Hydrodynamics of Large-Scale Fuel-Coolant Interactions
M. Baines, S. J. Board, N. E. Buttery, R. W. Hall
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 27-39
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32503
Critical Experiments with Concrete-Reflected Fast Test Reactor Fuel Pins in Water
S. R. Bierman, B. M. Durst, E. D. Clayton, B. W. Howes
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 40-46
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32504
Control of Oxygen, Hydrogen, and Tritium in Sodium Systems at Experimental Breeder Reactor II
Marilyn M. Osterhout
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 47-50
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32505
The Analysis of Boiling Water Reactor Long-Term Cooling
R. T. Lahey, Jr., P. S. Kamath
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 51-60
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32506
Development of a Removable Closure for Large Cavities in High Temperature Reactor Prestressed Concrete Reactor Vessels
S. R. Speidel, W. H. Plettenberg
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 61-69
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32507
Acoustic Measurement of Penetration of Liquid Sodium into Limestone Concrete
H. J. Sutherland, J. E. Smaardyk, L. A. Kent
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 70-79
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32508
The Uncertainty in Accident Consequences Calculated by Large Codes due to Uncertainties in Input
Dong H. Nguyen
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 80-91
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32509
In-Reactor Measurement of Neutron Absorber Performance
G. W. Hollenberg, J. L. Jackson, J. A. Basmajian
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 92-101
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32510
Implications of In-Channel Plugging During Fast Reactor Overpower Excursions
David W. Varela, William E. Kastenberg, Vijay K. Dhir
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 102-114
Technical Paper | Nuclear Power Reactor Safety / Reactor Siting | doi.org/10.13182/NT80-A32511
A Uranium-Plutonium-Neptunium Fuel Cycle to Produce Isotopically Denatured Plutonium
P. Wydler, W. Heer, P. Stiller, H. U. Wenger
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 115-120
Technical Paper | Nuclear Power Reactor Safety / Fuel Cycle | doi.org/10.13182/NT80-A32512
Isotope Dilution Alpha Spectrometry for the Determination of Plutonium Concentration in Irradiated Fuel Dissolver Solution: IDAS and R-IDAS
M. V. Ramaniah, H. C. Jain, S. K. Aggarwal, S. A. Chitambar, V. D. Kavimandan, A. I. Almaula, P. M. Shah, A. R. Parab, V. L. Sant
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 121-128
Technical Paper | Nuclear Power Reactor Safety / Chemical Processing | doi.org/10.13182/NT80-A32513
Pellet and Sphere-Pac (U,Pu)C Fuel Comparative Irradiation Tests
A. Delbrassine, L. Smith
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 129-135
Technical Paper | Nuclear Power Reactor Safety / Fuel | doi.org/10.13182/NT80-A32514
Development and Irradiation Performance of Uranium Aluminide Fuels in Test Reactors
J. M. Beeston, R. R. Hobbins, G. W. Gibson, W. C. Francis*
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 136-149
Technical Paper | Nuclear Power Reactor Safety / Fuel | doi.org/10.13182/NT80-A32515
A Model for the Transport of Radionuclides and Their Decay Products Through Geologic Media
H. C. Burkholder, E. L. J. Rosinger
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 150-158
Technical Paper | Nuclear Power Reactor Safety / Radioactive Waste | doi.org/10.13182/NT80-A32516
Intensity Measurements in X-Ray Fluorescence Analysis
T. V. Krishnan
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 159-164
Technical Paper | Nuclear Power Reactor Safety / Instrument | doi.org/10.13182/NT80-A32517
Measurement of the Ge(Li) Detector Efficiency for Gas Bomb Geometries
R. J. Gehrke, J. I. Anderson*, D. H. Meikrantz
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 165-173
Technical Paper | Nuclear Power Reactor Safety / Analysis | doi.org/10.13182/NT80-A32518
Liquid-Metal Fast Breeder Reactor Vented Assembly Hydraulic Modeling and Testing
James C. F. Wang, Allen E. Dubberley
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 186-195
Technical Paper | Reactor | doi.org/10.13182/NT80-A32481
A Continuous Glass Melter for Immobilization of Radioactive Waste
C. C. Chapman, J. L. Buelt
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 196-208
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32482
The Fixation of Radioiodine with Portland Cement. Part II: Radiation Stability Tests
Walter E. Clark, William B. Howerton
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 209-213
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32483
Dynamic Process Model of a Plutonium Oxalate Precipitator
G. M. Borgonovi, J. E. Hammelman, C. L. Miller
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 214-222
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32484
Alpha Waste Production and Proliferation Hazard of Different Fuel Cycles
Robert P. Schuman
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 223-232
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32485
A Production Facility for the Solidification of High-Level Radioactive Wastes
G. E. Bingham, B. R. Wheeler
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 233-242
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32486
Separation of Americium, Curium, and Trivalent Lanthanides from High-Level Wastes by Oxalate Precipitation: Experiments with Synthetic Waste Solutions
Charles W. Forsberg
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 243-252
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32487
The Sorption of Technetium and Iodine Radioisotopes by Various Minerals
R. Strickert, A. M. Friedman, S. Fried
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 253-266
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32488
Full-Scale In-Can Melting for Vitrification of Nuclear Wastes
H. Thomas Blair
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 267-273
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32489
Spent Fuel Heatup Following Loss of Water During Storage
Allen S. Benjamin, David J. McCloskey
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 274-294
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32490
Protection of Nuclear Power Plants Against Seism
C. Plichon, R. Gueraud, M. H. Richli, J. F. Casagrande
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 295-306
Nuclear Fuel Cycle | Reactor | doi.org/10.13182/NT80-A32491
The Use of Yttrium for the Recovery of Tritium from Lithium at Low Concentrations
Robert E. Buxbaum, Ernest F. Johnson
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 307-314
Nuclear Fuel Cycle | Chemical Processing | doi.org/10.13182/NT80-A32492
BeH2 as a Moderator in Minimum Critical Mass Systems
K. Subba Rao, M. Srinivasan
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 315-320
Technical Note | Reactor | doi.org/10.13182/NT80-A32493
Application of Sol-Gel Technology to Fixation of Nuclear Reactor Waste
W. J. Lackey, R. E. Blanco, A. L. Lotts
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 321-324
Technical Note | Radioactive Waste | doi.org/10.13182/NT80-A32494
Quality Influence on the Departure from Nucleate Boiling in Cross Flows Through Bundles
M. Cumo, G. E. Farello, J. Gasiorowski, G. Iovino, A. Naviglio
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 337-346
Technical Paper | Reactor | doi.org/10.13182/NT80-A17682
Thermomechanical Dynamic Behavior of the Solid Wall of a Pellet Fusion Reactor
Kenzo Miya, Joseph Silverman
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 347-359
Technical Paper | Reactor | doi.org/10.13182/NT80-A17683
Reduced Scale Simulations of Boiling Water Reactor Pool Swell: Some Limitations to the Scaling Laws
William G. Anderson, Richard P. Burke, Peter W. Huber, Ain A. Sonin
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 360-373
Technical Paper | Reactor | doi.org/10.13182/NT80-A17684
Some Comparisons Between Small-Scale Pool Swell Experiments and Model Predictions
Richard P. Burke, Peter W. Huber
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 374-379
Technical Paper | Reactor | doi.org/10.13182/NT80-A17685
Film Boiling and Vapor Explosion Phenomena
F. S. Gunnerson, A. W. Cronenberg
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 380-391
Technical Paper | Reactor | doi.org/10.13182/NT49-380
The Radiant Heat Transfer in the High Temperature Reactor Core After Failure of the Afterheat Removal Systems
G. Breitbach, H. Barthels
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 392-399
Technical Paper | Reactor | doi.org/10.13182/NT80-A17687
Optimal Size and Location of Nuclear Power Plants in Energy Parks
Hashem Akbari, Lawrence M. Grossman
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 400-409
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A17688
Evaluation Models for Uranium Exploration by Active Neutron Logging
W. A. Woolson, M. L. Gritzner
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 410-425
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17689
Fuel Survey in the Light Water Reactors Based on the Activity of the Fission Products
R. Beraha, G. Beuken, G. Frejaville, C. Leuthrot, Y. Musante
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 426-434
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17690
Two Near-Term Alternatives for Improved Nuclear Fuel Utilization
William V. Macnabb
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 435-442
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17691
On-Line Radiation Monitoring at a Nuclear Fuel Reprocessing Plant
K. J. Hofstetter, W. B. Stroube, Jr.,+ B. C. Henderson, G. A. Huff
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 443-457
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17692
Hybrids for Direct Enrichment and Self-Protected Fissile Fuel Production
R. W. Conn, F. Kantrowitz, W. F. Vogelsang
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 458-468
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17693
Volume Reduction of Organic Alpha Waste by Pyrohydrolysis
Alfred Chrubasik, Jürgen Hofmann, Horst Vietzke
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 469-473
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A17694
The Sorption of Actinides in Igneous Rocks
B. Allard, G. W. Beall, T. Krajewski+
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 474-480
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A17695
In-Pile Measurements of Zircaloy Creep and PCMI Deformation Comparative Evaluation of Ten Creep Correlations
Erik Kolstad
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 481-491
Technical Paper | Material | doi.org/10.13182/NT80-A17696
Experimental Evidence for the Use of the Gauss Function in the Functional Description of the Ductile-Brittle Transition of Ferritic Steels
Gerhard Hofer, Chau Chun Hung
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 492-497
Technical Paper | Material | doi.org/10.13182/NT80-A17697
Experimental and Theoretical Determination of Helium Production in Copper and Aluminum by 14.8-MeV Neutrons
D. W. Kneff, Harry Farrar IV, F. M. Mann, R. E. Schenter
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 498-503
Technical Note | Material | doi.org/10.13182/NT80-A17698
The Routine Reassessment of Absorbed Dose in LiF/Polytetrafluorethylene Thermoluminescent Dosimeter Elements
D. T. Bartlett, A. F. McKinlay, P. A. Smith
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 504-509
Technical Note | Instrument | doi.org/10.13182/NT80-A17699
