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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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IEA report: Challenges need to be resolved to support global nuclear energy growth
The International Energy Agency published a new report this month outlining how continued innovation, government support, and new business models can unleash nuclear power expansion worldwide.
The Path to a New Era for Nuclear Energy report “reviews the status of nuclear energy around the world and explores risks related to policies, construction, and financing.”
Find the full report at IEA.org.
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A Differential Calorimeter for Radiation-Induced Power
Wm. Bradley Lewis
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 1-5
Technical Paper | doi.org/10.13182/NSE64-A18136
A Comparison of Methods of Determining Burnup on Uranium Dioxide Fuel Test Specimens
R. G. Hart, M. Lounsbury, R. W. Jones, M. J. F. Notley
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 6-17
Technical Paper | doi.org/10.13182/NSE64-A18137
Titanium and Titanium Alloys in Mercury - Some Observations on Corrosion and Inhibition
James Y. N. Wang
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 18-30
Technical Paper | doi.org/10.13182/NSE64-A18138
Theoretical and Experimental Study of Fatigue in Photomultiplier Tubes
I. Cantarell
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 31-48
Technical Paper | doi.org/10.13182/NSE64-A18139
The Calculation of the Thermal Utilization and Disadvantage Factor in Uranium/Water Lattices
Henry C. Honeck
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 49-68
Technical Paper | doi.org/10.13182/NSE64-A18140
Heat-Transfer Studies of Water Flow in Thin Rectangular Channels: Part I - Heat Transfer, Burnout, and Friction for Water in Turbulent Forced Convection
W. R. Gambill, R. D. Bundy
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 69-79
Technical Paper | doi.org/10.13182/NSE64-A18141
Heat-Transfer Studies of Water Flow in Thin Rectangular Channels: Part II - Boiling Burnout Heat Flux for Low-Pressure Water in Natural Circulation
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 80-89
Technical Paper | doi.org/10.13182/NSE64-A18142
The Application of “One-Group” Transport Theory to β-Ray Dosimetry
K. O'Brien, S. Samson, R. Sanna, J. E. McLaughlin
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 90-96
Technical Paper | doi.org/10.13182/NSE64-A18143
Gas Chromatography as Applied to Nuclear Technology - II. Analysis of the Hydrolysis Products of Uranium Carbides and Thorium Carbides
A. D. Horton, J. L. Botts
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 97-104
Technical Paper | doi.org/10.13182/NSE64-A18144
Reactions O17 (n, p)N17 and O18 (n, d)N17 with Reactor Neutrons
Saadia Amiel, Jacob Gilat
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 105-109
Technical Paper | doi.org/10.13182/NSE64-A18145
Production of Transuranium Elements in a Thermonuclear Explosion - Anacostia
R. W. Hoff, D. W. Dorn
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 110-112
Technical Paper | doi.org/10.13182/NSE64-A18146
Economy of Experiment in Dose Albedo
N. F. Shoemaker, C. M. Huddleston
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 113-115
Technical Paper | doi.org/10.13182/NSE64-A18147
Lattice-Parameter Measurements for Solid and Concentric Tubes of Uranium Fuel in Graphite Lattices
D. E. Wood, K. R. Birney, E. Z. Block
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 116-125
Technical Paper | doi.org/10.13182/NSE64-A18148
Elastic Scattering of Fast Neutrons from U235
A. B. Smith
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 126-129
Technical Paper | doi.org/10.13182/NSE64-A18149
Theoretical Analysis of the Exponential Experiment in Natural Uranium
Paul Michael
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 130-136
Technical Paper | doi.org/10.13182/NSE64-A18150
Release of Fission Products During In-Pile Melting of UO2
W.E. Browning, Jr., C.E. Miller, Jr., R.P. Shields,B.F. Roberts
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 151-162
Technical Paper | doi.org/10.13182/NSE64-1
Application of Synthesis Techniques to Problems Involving Time Dependence
S. Kaplan, O. J. Marlowe, J. Bewick
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 163-176
Technical Paper | doi.org/10.13182/NSE64-A18315
The Recovery of Protactinium and Uranium from Molten Fluoride Systems by Precipitation as Oxides
J. H. Shaffer, W. R. Grimes, G. M. Watson, D. R. Cuneo, J. E. Strain, M. J. Kelly
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 177-181
Technical Paper | doi.org/10.13182/NSE64-A18316
Inelastic Neutron Scattering in Liquid Methane and Liquid Parahydroge
W. L. Whittemore
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 182-188
Technical Paper | doi.org/10.13182/NSE64-A18317
The Leachability of Fission Products from Uranium-Impregnated Graphite Heated at High Temperature
Kazumi Iwamoto
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 189-199
Technical Paper | doi.org/10.13182/NSE64-A18318
Design of a Pressure Balanced Control Rod
F. K. Clements, A. D. Kartchner, R. S. Kern, W. B. Lewis
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 200-206
Technical Paper | doi.org/10.13182/NSE64-A18319
Methods for Determining the Energy Release in Hypothetical Fast-Reactor Meltdown Accidents
Richard B. Nicholson
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 207-219
Technical Paper | doi.org/10.13182/NSE64-A18320
Evaluation of Two-Region-Reactor Parameters by Random Noise Measurements
Allen R. Boynton, Robert E. Uhrig
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 220-229
Technical Paper | doi.org/10.13182/NSE64-A18321
Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity
E. Starr, H. Honeck, J. DeVilliers†
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 230-235
Technical Paper | doi.org/10.13182/NSE64-A18322
Determination of Cadmium Burnup in Reactor Control Rods by Neutron Radiography
Harold Berger, James H. Talboy, Joseph P. Tylka
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 236-241
Technical Paper | doi.org/10.13182/NSE64-A18323
Theory of Pulsing Techniques
Edward Garelis
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 242-245
Technical Paper | doi.org/10.13182/NSE64-A18324
The Effective Resonance Integral of Thorium Oxide Rods
Jakob Weitman
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 246-259
Technical Paper | doi.org/10.13182/NSE64-A18325
The Energy-Dependent Milne Problem with a Simple Scattering Kernel
M. M. R. Williams
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 260-270
Technical Paper | doi.org/10.13182/NSE64-A18326
A Nonlinear Analysis of a Reactor with Two Temperature Coefficients
Louis M. Shotkin
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 271-279
Technical Paper | doi.org/10.13182/NSE64-A18327
Fission-Gas Release from Pyrolytic-Carbon-Coated Fuel Particles During Irradiation
P. E. Reagan, F. L. Carlsen, R. M. Carroll
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 301-318
Technical Paper | doi.org/10.13182/NSE64-A20051
In-Pile Experiments on Meltdown of EBR-II Mark I Fuel Elements in Stagnant Sodium
C. E. Dickerman, E. S. Sowa, J. H. Monaweck, A. Barsell
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 319-328
Technical Paper | doi.org/10.13182/NSE64-A20052
Boundary Conditions for Parallel Channel Flow
J. F. Thorpe
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 329-334
Technical Paper | doi.org/10.13182/NSE64-A20053
A Digital Computer Solution for Space-Dependent Neutron Kinetics Equations
A. N. Nahavandi, R. F. Von Hollen
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 335-350
Technical Paper | doi.org/10.13182/NSE64-A20054
Temperature Dependence of Neutron-Pulse Parameters in H2O
W. W. Clendenin
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 351-362
Technical Paper | doi.org/10.13182/NSE64-A20055
An Eigenvalue Method for the Calculation of Nuclear Burnup
G. D. Joanou, J. R. Triplett, R. M. Wagner
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 363-369
Technical Paper | doi.org/10.13182/NSE64-A20056
An Improved Spherical-Harmonics Method
W. R. Conkie
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 370-375
Technical Paper | doi.org/10.13182/NSE64-A20057
Neutron-Spectrum Measurements in H2O, CH2 and C6H6
J. C. Young, G. D. Trimble, Y. D. Naliboff, D. H. Houston, J. R. Beyster
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 376-399
Technical Paper | doi.org/10.13182/NSE64-A20058
Direct-Contact Core Systems
R. Philip Hammond, John R. Humphreys, Jr.
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 421-425
Technical Paper | doi.org/10.13182/NSE64-A18759
Fission-Product Behavior in Direct-Contact-Core Liquid-Metal-Fueled Reactors
Richard M. Bidwell
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 426-434
Technical Paper | doi.org/10.13182/NSE64-A18760
Delayed Neutron Economy and Control in a Direct-Contact-Core Liquid-Metal-Fueled Reactor
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 435-442
Technical Papers | doi.org/10.13182/NSE64-A18761
The Effect of Axial Heat Conduction in Fuel Plates on Maximum Heat Flow Rates and Temperatures
J. R. Fagan, J. O. Mingle
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 443-447
Technical Paper | doi.org/10.13182/NSE64-A18762
Intercomparison of Fast-Neutron Flux Monitors in a Hollow Fuel Element in Pluto
D. M. Clare, W. H. Martin, B. T. Kelly
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 448-458
Technical Paper | doi.org/10.13182/NSE64-A18763
Numerical Integration of the Spherical-Harmonics Equations
H. Waldinger, J. Agresta, G. Goertzel
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 459-467
Technical Paper | doi.org/10.13182/NSE64-A18764
Determination of Fast-Neutron Dose by Nickel Activation
W. H. Martin, D. M. Clare
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 468-473
Technical Paper | doi.org/10.13182/NSE64-A18765
Measurements of Leakage-Neutron Energy Spectra
C. A. Anderson, Jr., T. J. Thompson
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 474-480
Technical Paper | doi.org/10.13182/NSE64-A18766
Reactor Kinetics Analysis by an Inverse Method
Raymond L. Murray, Carroll R. Bingham, Chreston F. Martin
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 481-490
Technical Paper | doi.org/10.13182/NSE64-A18767
Neutron Transport in Cylindrical Rods
K. Bingham Cady, Melville Clark, Jr.
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 491-507
Technical Paper | doi.org/10.13182/NSE64-A18768
Closed-Loop Dynamics of Nuclear Rocket Engines with Topping Turbine Drive
Harold P. Smith, Jr.
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 508-513
Technical Paper | doi.org/10.13182/NSE64-A18769
Fuel-Importance Function and Minimum Critical Mass
Masuhiko Otsuka
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 514-517
Technical Paper | doi.org/10.13182/NSE64-A18770
Treat Study of the Penetration of Molten Uranium and U/5 wt% Fs Alloy through Type 304 Stainless Steel
C. M. Walter, C. E Dickerman
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 518-524
Technical Paper | doi.org/10.13182/NSE64-A18771