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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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
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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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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:
Phase Equilibria in the Plutonium-Cerium-Copper System
L. J. Wittenberg, D. E. Etter, J. E. Selle, P. A. Tucker
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE65-A19253
Energy Distributions of Fission Fragments from Uranium Dioxide Films
Steve Kahn, Randall Harman, Vernon Forgue
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 8-20
Technical Paper | doi.org/10.13182/NSE65-A19254
Radiometric Sensing of Atomic Hydrogen in Trace Quantities
Richard L. Bersin
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 21-27
Technical Paper | doi.org/10.13182/NSE65-A19255
A Last-Collision Approach to Calculating the Angular Distribution of Fast Neutrons Penetrating a Shield
R. L. French
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 28-33
Technical Paper | doi.org/10.13182/NSE65-A19256
Neutron-Spectrum Measurements in H2O and D2O
J. C. Young, J. M. Neill, D. H. Houston, J. R. Beyster
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 34-44
Technical Paper | doi.org/10.13182/NSE65-A19257
Measurement of the U235 Neutron Capture-to-Fission Ratio, α, for Incident Neutron Energies from 3.25 eV to 1.8 keV
G. deSaussure, L. W. Weston, R. Gwin, J. E. Russell and R. W. Hockenbury
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 45-57
Technical Paper | doi.org/10.13182/NSE65-A19258
Criticality Calculations for Uniform Water-Moderated Lattices
L. E. Strawbridge, R. F. Barry
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 58-73
Technical Paper | doi.org/10.13182/NSE65-A19259
Pulsed-Decay and Extrapolation-Length Measurements in Graphite
S. K. Davis, J. A. De Juren, M. Reier
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 74-81
Technical Paper | doi.org/10.13182/NSE65-A19260
Improvements to the Theory of Resonance Escape in Heterogeneous Fuel: II. The Dancoff Factor and the Equivalence Theorem in Cluster-Type Fuel
D. C. Leslie, A. Jonsson
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 82-89
Technical Paper | doi.org/10.13182/NSE65-A19261
On the Theory of Space-Dependent Neutron Spectra in Heterogeneous Reactors II
Helmut Kunze
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 90-97
Technical Paper | doi.org/10.13182/NSE65-A19262
Effect of Resonance Correction to Group Flux in Fast-Reactor Doppler-Effect Calculation
H. H. Hummel, R. N. Hwang
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 98-99
Technical Note | doi.org/10.13182/NSE65-A19263
Mass-Fission-Yield Curve for Americium-241
R. R. Rickard, C. F. Goeking, E. I. Wyatt
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 115-118
Technical Paper | doi.org/10.13182/NSE65-A28135
Dynamic Analysis of Coolant Circulation in Boiling-Water Nuclear Reactors — Part I
C. K. Sanathanan, J. C. Carter, F. Miraldi
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 119-129
Technical Paper | doi.org/10.13182/NSE65-A28136
Dynamic Analysis of Coolant Circulation in Boiling-Water Nuclear Reactors — Part II
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 130-137
Technical Paper | doi.org/10.13182/NSE65-A28137
Differential Dose-Rate Measurements of Backscattered Gamma Rays from Concrete, Aluminum and Steel
L. G. Haggmark, T. H. Jones, N. E. Scofield, W. J. Gurney
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 138-149
Technical Paper | doi.org/10.13182/NSE65-A28138
Criticality of Homogeneous Plutonium Oxide-Plastic Compacts at H:Pu=15
C. R. Richey, J. D. White, E. D. Clayton, R. C. Lloyd
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 150-158
Technical Paper | doi.org/10.13182/NSE65-A28139
The Decay of Equilibrium Neutron Flux Inside Beryllium Blocks at Different Temperatures
I. C. Goyal, L. S. Kothari
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 159-166
Technical Paper | doi.org/10.13182/NSE65-A28140
Equilibrium Spectra and Diffusion Lengths of Neutrons in Semi-Infinite Moderator Block: Part II: Effect of ‘Trapped’ and Cold Neutrons
P. S. Grover, L. S. Kothari
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 167-169
Technical Paper | doi.org/10.13182/NSE65-A28141
New Approximate Solution of Space- and Energy-Dependent Reactor Kinetics
Tsutomu Hoshino, Jiro Wakabayashi, Shigenori Hayashi
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 170-182
Technical Paper | doi.org/10.13182/NSE65-A28142
A Simplified Nonlinear Model for Qualitative Study of Reactor Power-Distribution Transients
H. Hurwitz, Jr.
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 183-187
Technical Paper | doi.org/10.13182/NSE65-A28143
Nuclear-Fuel-Depletion Measuring Device
L. B. Freeman
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 188-189
Technical Note | doi.org/10.13182/NSE65-A28144
Fission-Product Effects in Molten Chloride Fast-Reactor Fuels
M. G. Chasanov
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 189-190
Technical Note | doi.org/10.13182/NSE65-A28145
Neutron Diffusion Theory
J. D. Stewart
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 190-192
Technical Note | doi.org/10.13182/NSE65-A28146
The Energy-Dependent Total Neutron Cross Section of Polyethylene
S. B. Armstrong
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 192-194
Technical Note | doi.org/10.13182/NSE65-A28147
Inelastic Scattering of Slow Neutrons by Zirconium and Titanium Hydrides
S. S. Pan, F. J. Webb
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 194-197
Technical Note | doi.org/10.13182/NSE65-A28148
Some Remarks on the Reduction of Thermal-Neutron Activation Rates to a Differential Spectrum
H. Ibarra, R. Sher
Nuclear Science and Engineering | Volume 23 | Number 2 | October 1965 | Pages 197-199
Technical Note | doi.org/10.13182/NSE65-A28149
Fission-Gas Release from Pyrolytic-Carbon-Coated Fuel Particles During Irradiation at 2000 to 2500°F
P. E. Reagan, J. G. Morgan and O. Sisman
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 215-223
Technical Paper | doi.org/10.13182/NSE65-A19554
Measured and Predicted Thermal- and Fast-Neutron Fluxes in Air-Filled Annular Ducts
J. Nilsson and R. Sandlin
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 224-233
Technical Paper | doi.org/10.13182/NSE65-A19555
An Analogy Between the Variational Principles of Reactor Theory and those of Classical Mechanics
S. Kaplan
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 234-237
Technical Paper | doi.org/10.13182/NSE65-A19556
Analysis of (n, 2n) Cross Sections for Medium and Heavy Mass Nuclei
S. Pearlstein
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 238-250
Technical Paper | doi.org/10.13182/NSE65-A19557
Diffusion Length for Arbitrarily Anisotropic Scattering
E. Inönü and A. I. Usseli
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 251-255
Technical Paper | doi.org/10.13182/NSE65-A19558
The Age of Fission Neutrons to Indium Resonance Energy in Zirconium-Water Mixtures Part I—Experiment
R. K. Paschall
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 256-263
Technical Paper | doi.org/10.13182/NSE65-A19559
Age of Fission Neutrons to Indium Resonance Energy in Water and Zirconium-Water Mixtures (Part II—Theory)
Harry Alter
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 264-271
Technical Paper | doi.org/10.13182/NSE65-A19560
The Calculation of Collision Probabilities in Cluster-Type Fuel Elements
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 272-290
Technical Paper | doi.org/10.13182/NSE23-03-272
The Asymptotic Angular-Dependent Leakage Spectrum of Thermal Neutrons
R. Kladnik
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 291-298
Technical Paper | doi.org/10.13182/NSE65-A19562
Energy Loss by Fission Fragments in Nitrogen
Robert C. Axtmann and John T. Sears
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 299-305
Technical Paper | doi.org/10.13182/NSE65-A19563
Evaluation of Thermocouple Thermal-Loading Errors for a Surface-Attached Thermocouple on a Flat-Plate Fuel Element
J. H. Brindley
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 313-328
Technical Paper | doi.org/10.13182/NSE65-A21067
Axial Heat Conduction in Reactor Fuel Elements
J. F. Thorpe
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 329-334
Technical Paper | doi.org/10.13182/NSE65-A21068
The Solubility of Helium in Uranium Dioxide
Firooz Rufeh, Donald R. Olander and Thomas H. Pigford
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 335-338
Technical Paper | doi.org/10.13182/NSE65-A21069
An Attempt to Measure Directly the Slowing Down Age of (D,D) Neutrons in Paraffin
B. Grimeland and G. Seierstad
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 339-343
Technical Paper | doi.org/10.13182/NSE65-A21070
Calculation of Differential Fast-Neutron Spectra from Threshold-Foil Activation Data by Least-Squares Series Expansion Methods
G. Di Cola and A. Rota
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 344-353
Technical Paper | doi.org/10.13182/NSE65-A21071
Thermal-Neutron-Induced-Recoil Defects in Cadmium Sulfide
Robert B. Oswald, Jr., and Chihiro Kikuchi
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 354-360
Technical Paper | doi.org/10.13182/NSE65-A21072
Study of a Slightly Enriched UO2 Lattice with H:U=0.42 — Measurement and Analysis
W. Baer, J. Hardy, Jr., D. Klein, J. J. Volpe, B. L. Palowitch and F. S. Frantz, Jr.
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 361-367
Technical Paper | doi.org/10.13182/NSE65-A21073
Resonance Capture and Doppler Coefficient in Cylindrical Uranium Fuel Elements
T. D. Beynon, I. S. Grant
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 368-379
Technical Paper | doi.org/10.13182/NSE65-A21074
Polarization Effects on Neutron Transport
George I. Bell and Walter B. Goad
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 380-391
Technical Paper | doi.org/10.13182/NSE65-A21075
Doppler Coefficient Measurements for 235U in Fast-Reactor Spectra
P. I. Amundson, J. M. Gasidlo
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 392-393
Technical Note | doi.org/10.13182/NSE65-A21076
Thermal Disadvantage Factors in Very Undermoderated Water-Uranium Oxide Lattices
Allen R. Boynton
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 393-395
Technical Note | doi.org/10.13182/NSE65-A21077
A Method for Computing
G. C. Pomraning
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 395-397
Technical Note | doi.org/10.13182/NSE65-A21078
Equivalence of the Time Optimal and Minimax Solutions to the Xenon Shutdown Problem
John J. Roberts, Harold P. Smith, Jr.
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 397-399
Technical Note | doi.org/10.13182/NSE65-A21079
