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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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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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
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Seven-Rod Bundle, Natural-Circulation, Stability and Burn-Out Tests with Water at up to 28 Atmospheres Pressure
R. W. Bowring, C. L. Spigt
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE65-A19756
Purification of Beryllium by Acetylacetone — EDTA Solvent Extraction: Procedure and Chemistry
C. E. L. Bamberger, H. F. McDuffie, C. F. Baes, Jr.
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 14-19
Technical Paper | doi.org/10.13182/NSE65-A19757
Measurements of the Epicadmium Capture-to-Fission Cross-Section Ratio in U235
D. E. Conway, H. D. Cook, S. B. Gunst
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 20-23
Technical Paper | doi.org/10.13182/NSE65-A19758
Corrosion of Carbon Steel by Boiling and Superheated Mercury
A. H. Fleitman, A. J. Romano and C. J. Klamut
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 24-32
Technical Paper | doi.org/10.13182/NSE65-A19759
Comparisons of Measured and Calculated Neutron Fluxes in Laminated Iron and Heavy Water
Erkki J. Aalto
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 33-39
Technical Paper | doi.org/10.13182/NSE65-A19760
Neutron Thermalization Studies in Graphite
K. Serdula, J. Young
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 40-50
Technical Paper | doi.org/10.13182/NSE65-A19761
Stable Numerical Solutions of the Reactor Kinetics Equations
K. F. Hansen, B. V. Koen, W. W. Little, Jr.,
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 51-59
Technical Paper | doi.org/10.13182/NSE65-A19762
About the Generalization of Amouyal-Benoist's Method for Calculating Disadvantage Factors and Flux Distributions in Two-region Cells
Z. Weiss
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 60-77
Technical Paper | doi.org/10.13182/NSE65-A19763
Improvements to the Theory of Resonance Escape in Heterogeneous Fuel: I. Regular Arrays of Fuel Rods
D. C. Leslie, J. G. Hill, A. Jonsson
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 78-86
Technical Paper | doi.org/10.13182/NSE65-A19764
The Extrapolation Distance at the Surface of a Grey Cylindrical Control Rod
N. Spinks
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 87-93
Technical Paper | doi.org/10.13182/NSE65-A19765
The Effects of Flux Anisotropy on Thermal-Neutron Flux Perturbations
J. V. Walker
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 94-101
Technical Paper | doi.org/10.13182/NSE65-A19766
Measurement of Anisotropic Fast-Neutron Spectrum with Nuclear Emulsion
Tsutomu Iijima, Shoji Nomoto
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 102-110
Technical Paper | doi.org/10.13182/NSE65-A19767
Natural Vibration of Reactor Internals
George J. Bohm
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 143-152
Technical Paper | doi.org/10.13182/NSE65-A20233
Neutron Flux Measurement by Fission Tracks in Solids
R. L. Fleischer, P. B. Price and R. M. Walker
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 153-156
Technical Paper | doi.org/10.13182/NSE65-A20234
Neutron Spectra in Uranium Tubes
E. Johansson, E. Jonsson, M. Lindberg and J. Mednis
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 157-170
Technical Paper | doi.org/10.13182/NSE65-A20235
Some Numerical Experiments Concerning Space-Time Reactor Kinetics Behavior
J. B. Yasinsky and A. F. Henry
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 171-181
Technical Paper | doi.org/10.13182/NSE65-A20236
Approach to Equilibrium of a Neutron Pulse in a Multiplying System
A. K. Ghatak and S. Pearlstein
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 182-190
Technical Paper | doi.org/10.13182/NSE65-A20237
Spatially Dependent Transfer Function for Nuclear Systems
Chester D. Kylstra and Robert E. Uhrig
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 191-205
Technical Paper | doi.org/10.13182/NSE65-A20238
Complementary Use of Pulsed-Neutron and Reactor-Noise Measurements
S. R. Bierman, K. L. Garlid and R. W. Albrecht
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 206-214
Technical Paper | doi.org/10.13182/NSE65-A20239
A Solution of the Space-Energy-Angle-Dependent Neutron Slowing-Down Problem
Joseph J. McInerney
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 215-234
Technical Paper | doi.org/10.13182/NSE65-A20240
The Thermalization Theory with a Simple Scattering Kernel
Janusz Mika
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 235-243
Technical Paper | doi.org/10.13182/NSE65-A20241
Improved Rational Escape Probability in Lumped Absorbers
Charles N. Kelber
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 244-247
Technical Paper | doi.org/10.13182/NSE65-A20242
Some Input Functions for Anisotropic Neutron Scattering
W. Maurice Pritchard, Tino Ahrens
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 248-252
Technical Paper | doi.org/10.13182/NSE65-A20243
The Application of Dynamic Programing to Fuel Management Optimization
Ian Wall and Henri Fenech
Nuclear Science and Engineering | Volume 22 | Number 3 | July 1965 | Pages 285-297
Technical Paper | doi.org/10.13182/NSE65-A20933
Heat Transfer and Pressure Drop for Cross Flow through Banks of Multistart Helical Tubes with Uniform Inclinations and Uniform Longitudinal Pitches
P. V. Gilli
Nuclear Science and Engineering | Volume 22 | Number 3 | July 1965 | Pages 298-314
Technical Paper | doi.org/10.13182/NSE65-A20934
Neutron Penetration Factors Obtained by Using Adjoint Transport Calculations
G. E. Hansen and H. A. Sandmeier
Nuclear Science and Engineering | Volume 22 | Number 3 | July 1965 | Pages 315-320
Technical Paper | doi.org/10.13182/NSE65-A20935
Neutron-Wave Propagation Using the P1 Approximation
Glen A. Mortensen and Harold P. Smith, Jr.
Nuclear Science and Engineering | Volume 22 | Number 3 | July 1965 | Pages 321-327
Technical Paper | doi.org/10.13182/NSE65-A20936
An Asymptotically Correct Approximation to the Multidimensional Transport Equation
G. C. Pomraning
Nuclear Science and Engineering | Volume 22 | Number 3 | July 1965 | Pages 328-338
Technical Paper | doi.org/10.13182/NSE65-A20937
Reflection and Transmission by a Strongly Absorbing Slab
André Mackel
Nuclear Science and Engineering | Volume 22 | Number 3 | July 1965 | Pages 339-349
Technical Paper | doi.org/10.13182/NSE65-A20938
Geologic, Hydrologic, and Safety Considerations in the Storage of Radioactive Wastes in a Vault Excavated in Crystalline Rock
J. F. Proctor, I. W. Marine
Nuclear Science and Engineering | Volume 22 | Number 3 | July 1965 | Pages 350-365
Technical Paper | doi.org/10.13182/NSE65-A20939
Equilibrium Spectra and Diffusion Lengths of Neutrons in Semi-Infinite Moderator Block—Part I
P. S. Grover and L. S. Kothari
Nuclear Science and Engineering | Volume 22 | Number 3 | July 1965 | Pages 366-372
Technical Paper | doi.org/10.13182/NSE65-A20940
Formation of Se77m, Sr87m, Cd111m and Ba137m by Reactor Spectrum Neutrons for Use in Activation Analysis
Henry H. Kramer and Werner H. Wahl
Nuclear Science and Engineering | Volume 22 | Number 3 | July 1965 | Pages 373-382
Technical Paper | doi.org/10.13182/NSE65-A20941
Iron-54(n,p) Cross-Section Measurement
Edward E. Carroll, Jr., George G. Smith
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 411-415
Technical Paper | doi.org/10.13182/NSE65-A20626
Half-Life Determinations by Direct Decay
K. F. Flynn, L. E. Glendenin, E. P. Steinberg
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 416-419
Technical Paper | doi.org/10.13182/NSE65-A20627
Performance of Prototype Experimental Gas-Cooled Reactor Fuel Under Extreme Conditions
M. F. Osborne, E. L. Long, Jr., J. G. Morgan
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 420-433
Technical Paper | doi.org/10.13182/NSE65-A20628
The Electrical and Thermal Conductivity of Liquid Cesium to 1650 °C and the Critical Point of Cesium
Jack M. Hochman, Charles F. Bonilla
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 434-442
Technical Paper | doi.org/10.13182/NSE65-A20629
The Fine Adjustment of the Neutron Penetration in the NRN Method
E. Aalto, R. Fräki, K. Malén
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 443-450
Technical Paper | doi.org/10.13182/NSE65-A20630
A New Analytical Solution of the Energy-Dependent Boltzmann Equation
Nikolai Papmehl
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 451-454
Technical Paper | doi.org/10.13182/NSE65-A20631
Calculation and Measurement of the Fast-Neutron Differential Dose Albedo for Concrete
R. E. Maerker, F. J. Muckenthaler
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 455-462
Technical Paper | doi.org/10.13182/NSE65-A20632
Two-Phase Pressure Gradients in the Approach Region to Critical Flow
Amir N. Nahavandi, Richard F. Von Hollen
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 463-469
Technical Paper | doi.org/10.13182/NSE65-A20633
Time Optimal Solution to the Reactivity-Xenon Shutdown Problem
John J. Roberts, Harold P. Smith, Jr.
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 470-478
Technical Paper | doi.org/10.13182/NSE65-A20634
Some Applications of a Multimode Generalization of the Inhour Formula
A. F. Henry, S. Kaplan
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 479-486
Technical Paper | doi.org/10.13182/NSE65-A20635
Resonance Integral for the Doppler Measurement in Fast Reactors by the Foil-Activation Technique
A. B. Reynolds
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 487-489
Technical Note | doi.org/10.13182/NSE65-A20636
On Transient Phenomena in Thermalization
Anthony Leonard
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 489-490
Technical Note | doi.org/10.13182/NSE65-A20637
About the Influence of Resonance Overlapping on Calculated Doppler-Coefficients of Fast Reactors
R. Froelich, K. Ott
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 490-492
Technical Note | doi.org/10.13182/NSE65-A20638
Electron and Proton Fluxes in the Trapped Radiation Belts Originating from an Orbiting Nuclear Reactor
John C. Ringle
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 492-494
Technical Note | doi.org/10.13182/NSE65-A20639
Measurement and Calculation of Energy Deposition Due to Capture Gamma Rays Inside Annuli of Cadmium, Silver and Stainless Steel
A. W. Boyd, H. W. J. Connor, S. A. Kushneriuk
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 494-495
Technical Note | doi.org/10.13182/NSE65-A20640