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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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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.
Jump to:
The Solution of a Diffusion-Convective Corrosion Problem
Dale W. Lick, J. N. Tunstall
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 1-6
Technical Paper | doi.org/10.13182/NSE68-A20911
An Evaluation of the Departure from Nucleate Boiling in Bundles of Reactor Fuel Rods
L. S. Tong
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 7-15
Technical Paper | doi.org/10.13182/NSE68-A20912
The Total Neutron Cross Section of 115-Day Tantalum-182 from 0.01 to 1000 eV
G. E. Stokes, R. P. Schuman, and O. D. Simpson
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 16-23
Technical Paper | doi.org/10.13182/NSE68-A20913
Absolute Radiative Capture Cross Section for Fast Neutrons in 238U
H. O. Menlove and W. P. Poenitz
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 24-30
Technical Paper | doi.org/10.13182/NSE68-2
Neutron Scattering by Reactor-Grade Graphite
W. L. Whittemore
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 31-40
Technical Paper | doi.org/10.13182/NSE68-A20915
Slow-Neutron Inelastic Scattering and the Dynamics of Heavy Water
O. K. Harling
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 41-50
Technical Paper | doi.org/10.13182/NSE68-A20916
Central Reactivity Contributions of 244Cm, 239Pu, and 235U in a Bare Critical Assembly of Plutonium Metal
David Maxwell Barton
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 51-55
Technical Paper | doi.org/10.13182/NSE68-A20917
Measurement of Reactor Fluctuation Spectra and Subcritical Reactivity
C. W. Ricker, S. H. Hanauer, and E. R. Mann
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 56-64
Technical Paper | doi.org/10.13182/NSE68-A20918
Thermal-Neutron Decay in Small Systems
J. Dorning
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 65-80
Technical Paper | doi.org/10.13182/NSE68-A20919
Time-Dependent Neutron Thermalization in Finite Light Water Systems
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 81-92
Technical Paper | doi.org/10.13182/NSE68-A20920
A Modal Analysis of Neutron-Flux Spatial Oscillation
Masahide Imasaki and Torao Yanaru
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 93-105
Technical Paper | doi.org/10.13182/NSE68-A20921
On the Space-Energy Separability of the Fundamental Mode of the Neutron Transport Operator with Isotropic Scattering
Feroz Ahmed, A. K. Ghatak
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 106-118
Technical Paper | doi.org/10.13182/NSE68-A20922
A Transport Theory of Neutron Wave Propagation in Polycrystalline Media
James J. Duderstadt
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 119-127
Technical Paper | doi.org/10.13182/NSE68-A20923
A Three-Dimensional PN Spherical Harmonics Theory in Cylindrical Geometry
C. Maeder
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 128-138
Technical Paper | doi.org/10.13182/NSE68-A20924
Investigation of the Criticality of Low-Enrichment Uranium Cylinders
C. G. Chezem, E. J. Lozito
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Page 139
Technical Note | doi.org/10.13182/NSE68-A20925
An Interpretation of Reflector Savings Measured in Water-Moderated and Reflected Exponential Experiments
Henry H. Windsor
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 139-141
Technical Note | doi.org/10.13182/NSE68-A20926
The Approach to the Asymptotic Density of Neutrons Slowing Down from a Delta-Function Source
T. J. Williamson and R. W. Albrecht
Nuclear Science and Engineering | Volume 33 | Number 1 | July 1968 | Pages 141-143
Technical Note | doi.org/10.13182/NSE68-A20927
Placzek-Type Oscillations in General Neutron Slowing Down
M. Segev, S. Yiftah
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 147-150
Technical Paper | doi.org/10.13182/NSE68-A20652
PN Blackness Theory in Plane Geometry
S. P. Congdon, M. R. Mendelson
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 151-161
Technical Paper | doi.org/10.13182/NSE68-A20653
Optimal Control of Xenon-Power Spatial Transients
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 162-168
Technical Paper | doi.org/10.13182/NSE68-A20654
The Extrapolation Distance for a Black or Grey Cylindrical Neutron Absorber by the Spherical Harmonics Method
Bruno Pellaud
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 169-186
Technical Paper | doi.org/10.13182/NSE68-A20655
Slow Neutron Scattering from Water
R. M. Brugger
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 187-194
Technical Paper | doi.org/10.13182/NSE68-A20656
Inelastic Thermal-Neutron Scattering by Liquid D2O
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 195-208
Technical Paper | doi.org/10.13182/NSE68-A20657
Thermal-Neutron Diffusion in Light and Heavy Water
P. B. Parks, D. J. Pellarin, N. H. Prochnow, N. P. Baumann
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 209-217
Technical Paper | doi.org/10.13182/NSE68-A20658
Measurement of the Decay of Thermal Neutrons in Aqueous Solutions of the Non-1/v Neutron Absorber Cadmium
L. G. Larsson, E. Möller
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 218-224
Technical Paper | doi.org/10.13182/NSE68-A20659
Determination of Reactor Kinetic Parameters by Photon Observation
Wayne K. Lehto, John M. Carpenter
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 225-237
Technical Paper | doi.org/10.13182/NSE68-A20660
Spatially Dependent Resonance Neutron Spectra in a Slab of Depleted Uranium
H. M Antunez, J. M. Neill
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 238-248
Technical Paper | doi.org/10.13182/NSE68-A20661
Description of Anisotropic Scattering in the Double Pl Method by Means of Anisotropy Functions
S. A. W. Gerstl, W. Kofink
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 249-251
Technical Note | doi.org/10.13182/NSE68-A20662
A Variational Approach to the Selection of the Direction Sets in the Discrete Sn Approximation to Neutron Transport Theory
Pekka Jauho, Heikki Kalli
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 251-254
Technical Note | doi.org/10.13182/NSE68-A20663
Numerical Solution of the Boltzmann Integral Equation—A Multigroup Benchmark Calculation
K. D. Lathrop
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 255-257
Technical Note | doi.org/10.13182/NSE68-A20664
Application of Variational Synthesis to the Optimal Control of a Point Reactor Model
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 257-260
Technical Note | doi.org/10.13182/NSE68-A20665
Analytic Resonance Integral Formulae
N. M. Steen
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 260-262
Technical Note | doi.org/10.13182/NSE68-A20666
Time and Space Relaxation Constants of Neutrons in a Proton Gas
M. M. R. Williams
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 262-264
Technical Note | doi.org/10.13182/NSE68-A20667
An Iterative Method for Evaluation of Period Measurements in a Reactor Containing an Intrinsic Neutron Source
F. W. A. Habermann, H. Walze
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 264-265
Technical Note | doi.org/10.13182/NSE68-A20668
Total Neutron Cross Section of Water
J. M. Neill, J. L. Russell, Jr., J. R. Brown
Nuclear Science and Engineering | Volume 33 | Number 2 | August 1968 | Pages 265-267
Technical Note | doi.org/10.13182/NSE68-A20669
Performance of Gas-Cooled Fast Reactors with Artificially Roughened Fuel Elements
Gilbert Melese-d'Hospital
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 271-283
Technical Paper | doi.org/10.13182/NSE68-A19234
Monte Carlo Integration of the Adjoint Gamma-Ray Transport Equation
M. H. Kalos
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 284-290
Technical Paper | doi.org/10.13182/NSE68-A19235
Monte Carlo Calculations of the Nucleon-Meson Cascade in Iron Initiated by 1- and 3-GeV Protons and Comparison with Experiment
T. W. Armstrong, R. G. Alsmiller, Jr.
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 291-296
Technical Paper | doi.org/10.13182/NSE68-A19236
Multigroup Treatment of Neutron Transport in Plane Geometry
T. Yoshimura, S. Katsuragi
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 297-302
Technical Paper | doi.org/10.13182/NSE68-A19237
On the Quantum-Mechanical Foundations of the Neutron Transport Theory
P. Jauho, D. O. Riska
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 303-306
Technical Paper | doi.org/10.13182/NSE68-A19238
Solution of the Two-Group Neutron Transport Equation—I
D. R. Metcalf, P. F. Zweifel
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 307-317
Technical Paper | doi.org/10.13182/NSE68-A19239
Solution of the Two-Group Neutron Transport Equation—II
D. R. Metcalf and P. F. Zweifel
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 318-326
Technical Paper | doi.org/10.13182/NSE68-A19240
Numerical Solutions of Boundary Value Problems
J. W. Lucey, K. F. Hansen
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 327-335
Technical Paper | doi.org/10.13182/NSE68-A19241
Hexagonal Lattice Coordinates
Bernard H. Duane
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 336-339
Technical Paper | doi.org/10.13182/NSE68-A19242
Some Consideration of Dose Buildup Factor for a 60Co Cylindrical Source with Shell-Shaped Shield
Yutaka Furuta, Yoshihiko Kanemori
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 340-341
Technical Note | doi.org/10.13182/NSE68-A19243
First-Flight Escape Probability for Bodies Containing a Central Black Region
Owen J. Smith, Raymond L. Murray
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 341-343
Technical Note | doi.org/10.13182/NSE33-03-341
Space-Dependent Effects in Rossi-Alpha Experiments
Tsutomu Iijima, Teruo Sugi, Hideo Ezure, Mineo Kasai
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 344-348
Technical Note | doi.org/10.13182/NSE68-A19245
Resonance Absorption in a Lump Surrounded by a Homogeneous Medium Containing the Same Resonance Absorber
L. I. Tirén
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 348-350
Technical Note | doi.org/10.13182/NSE68-A19246
Infinite Dilution Resonance Absorption Integrals of Hafnium
J. W. Rogers, J. J. Scoville
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 350-352
Technical Note | doi.org/10.13182/NSE68-A19247
An Empirical Study of the Convergence of the Eigenfunction Expansion Method for Investigating Neutron Wave Propagation
R. S. Booth, W. A. Swansiger
Nuclear Science and Engineering | Volume 33 | Number 3 | September 1968 | Pages 352-354
Technical Note | doi.org/10.13182/NSE68-A19248
