ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
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:
On the Use of Acoustic Waves in Nuclear Power Reactors to Determine Average Void Fractions
J. A. Bonnet, Jr., R. K. Osborn
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 1-4
Technical Paper | doi.org/10.13182/NSE71-A21240
Analysis of Heterogeneity and Sodium-Void Effects in a 2700-Liter Uranium Carbide Fast Core, ZPR-6 Assembly 5
R. A. Karam, J. E. Marshall, K. D. Dance
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 5-26
Technical Paper | doi.org/10.13182/NSE71-A21241
The Transmission of Xenon-133 Through Activated Charcoal Adsorber Beds
K. B. Lee, Richard Madey
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 27-31
Technical Paper | doi.org/10.13182/NSE71-A21242
Gamma-Ray Attenuation at Energies of Approximately 6 and 8 MeV
W. Reed Johnson, Daniel H. Risher, James E. Rogers, William L. Thompson
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 32-41
Technical Paper | doi.org/10.13182/NSE71-A21243
Measurements of Time-Dependent Energy Spectra of Beta Rays from Uranium-235 Fission Fragments
N. Tsoulfanidis, B. W. Wehring, M. E. Wyman
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 42-53
Technical Paper | doi.org/10.13182/NSE71-A21244
The Average Number of Neutrons Emitted in the Spontaneous Fission of Some Even-Even Heavy Nuclides
C. J. Orth
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 54-57
Technical Paper | doi.org/10.13182/NSE71-A21245
Total Neutron Cross Section and Resonance Parameters of Promethium-147
J. W. Codding, Jr., R. L. Tromp, F. B. Simpson
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 58-65
Technical Paper | doi.org/10.13182/NSE71-A21246
Phase-Space Reduction in Neutron Diffusion Calculations
A. A. Harms, A. L. Babb
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 66-73
Technical Paper | doi.org/10.13182/NSE71-A21247
Multiple Weighting Functions in Fast Reactor Space-Energy Synthesis
R. J. Neuhold
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 74-86
Technical Paper | doi.org/10.13182/NSE71-A21248
Pressure Distribution for Axisymmetric Two-Dimensional Flow in a Plenum During Coolant Expulsion
T. C. Chawla, B. M. Hoglund
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 87-90
Technical Note | doi.org/10.13182/NSE71-A21249
Critical Heat Flux and Pressure Drop Tests with Parallel Upflow of High Pressure Water in Bundles of Twenty 1/2-in. Rods
B. W. LeTourneau, S. J. Green
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 90-104
Technical Note | doi.org/10.13182/NSE71-A21250
Monte Carlo Calculation of the Thermal Neutron Activation in Light-Water-Moderated Uranium Cells Using ENDF/B Cross-Section Data
John J. Volpe, William Baer
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 105-106
Technical Note | doi.org/10.13182/NSE71-A21251
A Fast Method of Computing the Contribution from Interference Scattering of Neutrons to the Integral J(θ, α, β)
Frej Wasastjerna
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 106-108
Technical Note | doi.org/10.13182/NSE71-A21252
Reduction of the Ray Effect in Discrete Ordinates Calculations
Robert E. Sullivan, Lynn U. Albers, Dahsoong Yu
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 108-114
Technical Note | doi.org/10.13182/NSE71-A21253
Determining Collision Variances from Adjoints
Harvey Amster
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 114-116
Technical Note | doi.org/10.13182/NSE71-A21254
Coarse Mesh Acceleration of Iterative Solution of Neutron Diffusion Equation
Shoichiro Nakamura
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 116-120
Technical Note | doi.org/10.13182/NSE71-A21255
Thermal Neutron Diffusion at the Ice-Water Phase Transition
P. M. Williams, F. J. Munno
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 120-122
Technical Note | doi.org/10.13182/NSE71-A21256
Consistent Criticality Estimates in Pulsed Neutron Experiments
A. A. Harms
Nuclear Science and Engineering | Volume 43 | Number 1 | January 1971 | Pages 122-124
Technical Note | doi.org/10.13182/NSE71-A21257
Variational Derivation of Discrete Ordinate-Like Approximations
M. Natelson
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 131-144
Technical Paper | doi.org/10.13182/NSE71-A21261
Energy-Dependent Neutron Transport Theory in Adjacent Half-Spaces
Pekka Jauho, Markku Rajamäki
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 145-153
Technical Paper | doi.org/10.13182/NSE71-A21262
Relationships Between Various Definitions of Prompt-Neutron Lifetime
Paul Nelson, Jr.
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 154-158
Technical Paper | doi.org/10.13182/NSE71-A21263
Successive Space-Energy Synthesis for Neutron Fluxes in Fast Reactors
J. E. Cockayne, K. O. Ott
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 159-172
Technical Paper | doi.org/10.13182/NSE71-A21264
Effect of Collapsing Cross-Section Data on Fast Breeder Physics Parameters
Raymond E. Alcouffe, Thomas J. Hirons, R. Douglas O'Dell
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 173-185
Technical Paper | doi.org/10.13182/NSE71-A21265
Radiation Transport in One-Dimensional Finite Systems—Part I: Development in the Anisotropic Source—Flux Iteration Technique
D. V. Gopinath, K. Santhanam
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 186-196
Technical Paper | doi.org/10.13182/NSE71-A21266
Radiation Transport in One-Dimensional Finite Systems—Part II: Gamma-Ray Transport Studies with ASFIT
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 197-211
Technical Paper | doi.org/10.13182/NSE71-A21267
Initial Size Distributions of Aerosols
George C. Lindauer, A. W. Castleman, Jr.
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 212-217
Technical Paper | doi.org/10.13182/NSE71-A21268
Stable Numerical Integration of Conservation Equations for Hydraulic Networks
T. A. Porsching, J. H. Murphy, J. A. Redfield
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 218-225
Technical Paper | doi.org/10.13182/NSE71-A21269
Application of the Adler-Adler Multilevel Formalism to Calculation of Uranium-235 Resonance Integrals
B. Frogner, S. Børresen
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 226-227
Technical Note | doi.org/10.13182/NSE71-A21270
Positive Reactivity from Replacement of Heavy Water by Light Water in the Coolant Channels of a Heavy-Water-Moderated Reactor
James H. Talboy, Edward J. Donahue, Albert W. Pierce, John J. Vronich
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 227-229
Technical Note | doi.org/10.13182/NSE71-A21271
Evaluation of Published Delayed-Neutron Parameters for Uranium-235 and Uranium-235 Heavy Water Systems
J. P. Church
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 229-233
Technical Note | doi.org/10.13182/NSE71-A21272
Titanium (n, p) Cross-Section Measurements
Yovan Lukic, Edward E. Carroll
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 233-235
Technical Note | doi.org/10.13182/NSE71-A21273
Multigroup Elastic Scattering Cross Sections for Heavy Elements
Herbert Henryson II
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 235-237
Technical Note | doi.org/10.13182/NSE71-A21274
Two-Dimensional Conduction Heat Transfer in Liquid-Metal Bonded Fast Reactor Fuel Elements with Pellet and Canning Eccentricity
L. Wolf, K. Johannsen
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 237-239
Technical Note | doi.org/10.13182/NSE71-A21275
Expected Number of Subassembly Failures Due to Hot Spot Occurrences
A. Amendola
Nuclear Science and Engineering | Volume 43 | Number 2 | February 1971 | Pages 239-240
Technical Note | doi.org/10.13182/NSE71-A21276
Heat Transfer to a Bingham Plastic in the Entrance Region of a Circular Tube
A. B. Samant, W. J. Marner
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 241-246
Technical Paper | doi.org/10.13182/NSE71-A19969
Dispersion of Radioactivity in a Closed Coolant System
S. A. Kushneriuk
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 247-256
Technical Paper | doi.org/10.13182/NSE71-A19970
The Absorbed Dose and Dose Equivalent from Negatively and Positively Charged Pions in the Energy Range 10 to 2000 MeV
R. G. Alsmiller, Jr., T. W. Armstrong, Barbara L. Bishop
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 257-266
Technical Paper | doi.org/10.13182/NSE71-A19971
Absolute Gamma-Ray Intensity Measurements of a SNAP-15A Heat Source
Melvin Reier
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 267-272
Technical Paper | doi.org/10.13182/NSE71-A19972
Differential Measurements of Fast-Neutron Air-Ground Interface Effects
R. L. French, L. G. Mooney
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 273-280
Technical Paper | doi.org/10.13182/NSE71-A19973
High Resolution Fission Cross Section of Uranium-235 from 20 eV to 100 keV
J. R. Lemley, G. A. Keyworth, B. C. Diven
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 281-285
Technical Paper | doi.org/10.13182/NSE71-A19974
Analysis of Exponential Experiments with Lattices of Plutonium in Heavy Water
Odelli Ozer
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 286-302
Technical Paper | doi.org/10.13182/NSE71-A19975
Neutron-Pulse Propagation in Multiplying Assemblies
M. W. Golay, K. B. Cady
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 303-314
Technical Paper | doi.org/10.13182/NSE71-A19976
A New Variational Method for the Pulsed-Neutron Problem
Feroz Ahmed, L. S. Kothari
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 315-318
Technical Paper | doi.org/10.13182/NSE71-A19977
A Temperature Formulation of the Space-Averaged Reactor Kinetics Equations
H. A. Kurstedt, Jr., G. H. Miley
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 319-327
Technical Paper | doi.org/10.13182/NSE71-A19978
Energy Modal Synthesis Method in Fast Reactor Analysis
Takashi Kiguchi, Shigehiro An, Akira Oyama
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 328-340
Technical Paper | doi.org/10.13182/NSE71-A19979
The Low-Energy Total Neutron Cross Section of Plutonium-242
T. E. Young, F.B. Simpson, R. E. Tate
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 341-342
Technical Note | doi.org/10.13182/NSE71-A19980
Optimum Refueling Order for Minimum Local Power Peaking Factor
Toshio Kawai, Takashi Kiguchi
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 342-345
Technical Note | doi.org/10.13182/NSE71-A19981
A Reformulation of the Reactor Kinetics Equations
Ronald J. Onega
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 345-348
Technical Note | doi.org/10.13182/NSE71-A19982
Note on Particular Solutions of the Transport Equation
K. D. Leuthäuser
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 348-349
Technical Note | doi.org/10.13182/NSE71-A19983
A Comparison of Federighi's with Marshak's Boundary Conditions
José Canosa
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 349-350
Technical Note | doi.org/10.13182/NSE71-A19984
Escape Probability for Cylinders
Raymond L. Murray
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 350-352
Technical Note | doi.org/10.13182/NSE71-A19985
