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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Analysis on the Primary System Radiation Control at Tsuruga Boiling Water Reactor Plant
Kenji Yamazaki, Shigeharu Fujita, Toshimasa Kamata, Yoshitake Morikawa, Kunio Numata, Kenji Osamura, Yoshinori Meguro
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 7-21
Technical Paper | Reactor | doi.org/10.13182/NT81-A32685
Two-Dimensional Neutronics Calculation for the High Yield Lithium Injection Fusion Energy Converter
Wayne R. Meier
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 22-31
Technical Paper | Reactor | doi.org/10.13182/NT81-A32686
Retrieval of Damaged Subassembly from Experimental Breeder Reactor II Primary Tank
Ronald W. King, Erwin C. Filewicz
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 32-42
Technical Paper | Reactor | doi.org/10.13182/NT81-A32687
An Analysis of the Thermal Behavior of a Stagnant Pool for Fast Reactor Safety
S. J. Hakim, T. H. Bauer, R. O. McNary
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 43-56
Technical Paper | Reactor | doi.org/10.13182/NT81-A32688
An Economic Model for Fuel Cycle Cost
Charles Abou-Ghantous
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 57-65
Technical Paper | Fuel Cycle | doi.org/10.13182/NT81-A32689
Rapid Dissolution of Plutonium Metal in Sulfamic Acid Followed by Conversion to a Nitric Acid Medium
Leonard W. Gray
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 66-72
Technical Paper | Chemical Processing | doi.org/10.13182/NT81-A32690
Mechanical Properties of Advanced Fuels Under Compressive Deformation
P. Werner, H. Blank
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 73-85
Technical Paper | Fuel | doi.org/10.13182/NT81-A32691
Film Boiling Behavior of a Pressurized Water Reactor Type Fuel Bundle
F. S. Gunnerson, D. T. Sparks, D. K. Kerwin
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 86-99
Technical Paper | Fuel | doi.org/10.13182/NT81-A32692
Depleted Uranium Dioxide Powder Flow Through Very Small Openings
S. L. Sutter, J. W. Johnston, P. C. Owzarski, J. Mishima, L. C. Schwendiman
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 100-104
Technical Paper | Fuel | doi.org/10.13182/NT81-A32693
Uranium Enrichment by the Separation Nozzle Method Within the Framework of German/Brazilian Cooperation
E. W. Becker, P. Nogueira Batista, H. Vlcker
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 105-114
Technical Paper | Isotopes Separation | doi.org/10.13182/NT81-A32694
Measurement of Sulfur-35 in the Coolant Gas of the Windscale Advanced Gas-Cooled Reactor
F. J. Sandalls
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 115-120
Technical Paper | Analysis | doi.org/10.13182/NT81-A32695
Nondestructive Analysis of Radwaste Containers
Yakov Ben-Haim, Ezra Elias, Alexander Knoll
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 121-128
Technical Paper | Technique | doi.org/10.13182/NT81-A32696
Response of Large Cavity Ion Chambers to Space Protons
John W. Wilson, Govind S. Khandelwal
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 129-133
Technical Paper | Technique | doi.org/10.13182/NT81-A32697
A Note on Transient Fuel Behavior Maps for Oxide Nuclear Reactor Fuel
R. J. DiMelfi
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 134-138
Technical Note | Fuel | doi.org/10.13182/NT81-A32698
Gamma-Induced Electron Emission from Conducting Surfaces
James D. Wolcott, J. N. Anno
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 139-140
Technical Note | Radiation | doi.org/10.13182/NT81-A32699
Calibration of Electrochemical Oxygen Meters for Sodium in Static Tests and in the Sodium Loop
N. P. Bhat, H. U. Borgstedt
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 153-161
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32660
Role of Condensation in Aerosol Source Term for Liquid-Metal Fast Breeder Reactor Containments
A. A. Emami, S. K. Loyalka
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 162-169
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32661
Tritium Breeding Management in the High Yield Lithium Injection Fusion Energy Chamber
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 170-178
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32662
Statistical Evaluation of Design-Error Related Nuclear Reactor Accidents
K. O. Ott, J. F. Marchaterre
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 179-188
Technical Paper | Nuclear Safety | doi.org/10.13182/NT81-A32663
The Benefits of Cycle Stretchout in Pressurized Water Reactor Extended-Burnup Fuel Cycles
R. A. Matzie, D. C. Leung, Y. Liu, R. W. Beekmann
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 189-197
Technical Paper | Fuel Cycle | doi.org/10.13182/NT81-A32664
Simplified Procedures for Fast Reactor Fuel Cycle and Sensitivity Analysis
Ahmed Badruzzaman, Martin Becker
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 198-213
Technical Paper | Fuel Cycle | doi.org/10.13182/NT81-A32665
Bow in Experimental Breeder Reactor II Reflector Subassemblies
J. A. Shields, Jr.
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 214-227
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32666
TREAT Test L5 Simulating an LMFBR Loss-of-Flow Accident with FTR-Type Irradiated Fuel
Richard Simms, Stephen M. Gehl, Robert K. Lo, Alan B. Rothman
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 228-245
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32667
Full-Fluence Tests of Experimental Thermosetting Fuel Rods for the High-Temperature Gas-Cooled Reactor
Ronald E. Bullock
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 246-259
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32668
An Analysis of Diffusional Ion Transport in Ocean Sediments: Subseafloor Disposal of Radioactive Waste
Herbert E. Nuttall, Asit K. Ray, E. James Davis
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 260-272
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT81-A32669
In-Reactor Creep Measurements
E. R. Gilbert, B. A. Chin
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 273-283
Technical Paper | Material | doi.org/10.13182/NT81-A32670
The Application of High Gradient Magnetic Separation in Nuclear Fuel Reprocessing
J. A. Williams, W. Baxter, G. Collins, K. Harding, C. M. Leslie, R. J. Sills
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 284-294
Technical Paper | Material | doi.org/10.13182/NT81-A32671
Fission Track Annealing and Fission Track Age-Temperature Relationship in Sphene
T. D. Märk, M. Pahl, R. Vartanian
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 295-305
Technical Paper | Technique | doi.org/10.13182/NT81-A32672
On the Minimum Overall Size of a Reflected Pebble-Bed Reactor
R. Chawla
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 306-309
Technical Note | Fission Reactor | doi.org/10.13182/NT81-A32673
An Empirical Equation for Estimating Nitric-Acid Extraction by Tri-n-Buytl Phosphate from Nitric Acid and Nitric-Acid/Sodium-Nitrate Solutions
J. C. Mailen
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 310-312
Technical Note | Chemical Processing | doi.org/10.13182/NT81-A32674
Calculation of Neutron Die-Away Times in a Large-Vehicle Portal Monitor
R. A. Lillie, R. T. Santoro, R. G. Alsmiller, Jr.
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 313-318
Technical Note | Analysis | doi.org/10.13182/NT81-A32675
Loss-of-Flow Transient Reactor Test Facility Tests L6 and L7 with Irradiated Liquid-Metal Fast Breeder Reactor Type Fuel
Richard Simms, Gerald E. Marsh, Alan B. Rothman, George S. Stanford
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 331-341
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32707
Criticality Experiments with Subcritical Clusters of Light Water Reactor Type Fuel Separated by a Flux Trap
S. R. Bierman, E. D. Clayton
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 342-346
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32708
A Method of Performing Shutdown Reactivity Measurements in Spent Nuclear Fuel Storage Pools
Samuel H. Levine, Mortimer A. Schultz, Daren Chang
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 347-353
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32709
Measurement and Calculation of the Effectiveness of the Gas-Cooled Fast Breeder Reactor Grid-Plate Shield
C. O. Slater, S. N. Cramer, D. T. Ingersoll, M. L. Williams, F. J. Muckenthaler, J. J. Manning, J. L. Hull
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 354-369
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32710
Neutronic Space-Time Effects with Thermal-Hydraulic Feedback in Large Homogeneous and Heterogeneous Liquid-Metal Fast Breeder Reactors
S. F. Su, Y. Orechwa, H. Henryson II
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 370-382
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32711
Geometrical View Factors for Radiative Heat Transfer Within Boiling Water Reactor Fuel Bundles
David A. Mandell
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 383-392
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32712
The Fabrication of Grid Spacer Assemblies for Liquid-Metal Fast Breeder Reactors
E. D. Jones, A. McBride, K. C. Thomas
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 393-400
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32713
Heat Transfer near Spacer Grids in Gas-Cooled Rod Bundles
M. A. Hassan, K. Rehme
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 401-414
Technical Paper | Fuel Cycle | doi.org/10.13182/NT81-A32714
A Comparison of Borosilicate Glass and Synthetic Minerals as Media for the Immobilization of High-Level Radioactive Waste
P. A. Tempest
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 415-425
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT81-A32715
An Equation-of-State of Xenon for Nonequilibrium Bubble Kinetics Calculations During Fast Transients
Morris Schwarzblat
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 426-427
Technical Note | Fission Reactor | doi.org/10.13182/NT81-A32716
Increases in Neutron Yield of 239Pu-Be(α,n) Sources—II
M. E. Anderson
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 428-430
Technical Note | Fission Reactor | doi.org/10.13182/NT81-A32717
Waterside Corrosion Correlations for Cr—1 Mo Steel in Liquid-Metal Fast Breeder Reactor Steam Generators
L. V. Hampton, G. J. Licina, P. Roy
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 431-434
Technical Note | Material | doi.org/10.13182/NT81-A32718
Radiation-Induced Outgassing from Several Metals
A. R. Shepherd, J. N. Anno
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 435-436
Technical Note | Material | doi.org/10.13182/NT81-A32719
Radiation-Induced Gas Evolution from Several Organic Liquids
Woon H. Chung, J. N. Anno
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 437-438
Technical Note | Material | doi.org/10.13182/NT81-A32720