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Division Spotlight
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.
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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Three nations, three ways to recycle plastic waste with nuclear technology
Plastic waste pollutes oceans, streams, and bloodstreams. Nations in Asia and the Pacific are working with the International Atomic Energy Agency through the Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative to tackle the problem. Launched in 2020, NUTEC Plastics is focused on using nuclear technology to both track the flow of microplastics and improve upstream plastic recycling before discarded plastic can enter the ecosystem. Irradiation could target hard-to-recycle plastics and the development of bio-based plastics, offering sustainable alternatives to conventional plastic products and building a “circular economy” for plastics, according to the IAEA.
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Fast Reactor Design Optimization System with a Method of Nonlinear Programming
Kotaro Inoue
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE73-A23252
On the Control of Spatial Xenon Oscillations
A. M. Christie, C. G. Poncelet
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 10-24
Technical Paper | doi.org/10.13182/NSE73-A23253
Measurement and Evaluation of Total Neutron Cross-Section Minima in Elemental Iron from 24 to 750 keV
K. A. Alfieri, R. C. Block, P. J. Turinsky
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 25-31
Technical Paper | doi.org/10.13182/NSE73-A23254
Low Energy Components of Scattered Gamma Radiation
Susumu Minato
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 32-40
Technical Paper | doi.org/10.13182/NSE73-A23255
Evaluation of Lumped Parameter Heat Transfer Techniques for Nuclear Reactor Applications
D. M. France, T. Ginsberg
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 41-51
Technical Paper | doi.org/10.13182/NSE73-A23256
The Energy Distribution of Delayed Fission Neutrons
S. Shalev, J. M. Cuttler
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 52-66
Technical Paper | doi.org/10.13182/NSE73-A23257
A New Method of Solving the Multimode Reactor Kinetics Equations
J. C. Turnage
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 67-76
Technical Note | doi.org/10.13182/NSE73-A23258
On a Multidirectional Modal Representation for Neutron Transport Analysis
A. A. Harms, S. A. Kushneriuk
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 76-78
Technical Note | doi.org/10.13182/NSE73-A23259
A Simple Analytic Transient Flux Expression for Use With Asymptotic Diffusion Theory
L. E. Beghian, I. A. Forbes, V. C. Rogers
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 78-83
Technical Note | doi.org/10.13182/NSE73-A23261
An Exact Analytical Solution of an Elementary Critical Condition
C. E. Siewert
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Page 78
Technical Note | doi.org/10.13182/NSE73-A23260
Absolute Neutron Yields from Alpha-Particle Interaction with Thick Targets of Natural Carbon
J. K. Bair
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 83-84
Technical Note | doi.org/10.13182/NSE73-A23262
Heat Conduction in the UO2-Cladding Composite Body with Simultaneous Solidification and Melting
Michael Epstein
Nuclear Science and Engineering | Volume 51 | Number 1 | May 1973 | Pages 84-87
Technical Note | doi.org/10.13182/NSE73-A23263
On the Mechanism of Uranium Dioxide-Sodium Explosive Interactions
Hans K. Fauske
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 95-101
Technical Paper | doi.org/10.13182/NSE73-A26584
Gamma-Ray Attenuation in Basement Ceilings
R. S. Reynolds
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 102-112
Technical Paper | doi.org/10.13182/NSE73-A26585
Gamma-Ray Spectra from the Interaction of 14-MeV Neutrons with Copper, Zirconium, and Antimony
Michael Stamatelatos, Bo Lawergren, Leon J. Lidofsky
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 113-118
Technical Paper | doi.org/10.13182/NSE73-A26586
Resonances Suitable for the Calibration of a Time-of-Flight Neutron Spectrometer
S. Wynchank, F. Rahn, H. S. Carmada, G. Hacken, M. Slagowitz, H. I. Liou, J. Rainwater, W. W. Havens, Jr.
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 119-123
Technical Paper | doi.org/10.13182/NSE73-A26587
A Measurement of the Fission Cross Section of Plutonium-241 Relative to Uranium-235
F. Käppeler, E. Pfletschinger
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 124-129
Technical Paper | doi.org/10.13182/NSE73-A26588
High Resolution Measurements of Neutron-Induced Fission Cross Sections for 233U, 235U, 239Pu and 241Pu Below 30 keV
J. Blons
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 130-147
Technical Paper | doi.org/10.13182/NSE73-A26589
The Application of Phase-Space Finite Elements to the One-Dimensional Neutron Transport Equation
W. F. Miller, Jr., E. E. Lewis, E. C. Rossow
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 148-156
Technical Paper | doi.org/10.13182/NSE73-A26590
One-Speed Neutron Transport Problems-Part I: Exact Transfer Matrix Formulation
Raphael Aronson
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 157-165
Technical Paper | doi.org/10.13182/NSE73-A26591
One-Speed Neutron Transport Problems-Part II: Slab Transmission and Reflection and Finite Reflector Critical Problems
Gerhard Caroll and Raphael Aronson
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 166-179
Technical Paper | doi.org/10.13182/NSE73-A26592
Higher Order Perturbation Method in Reactor Calculations
Hiroshi Mitani
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 180-188
Technical Paper | doi.org/10.13182/NSE51-180
Solution of the Space-Dependent Reactor Kinetics Equations in Three Dimensions
D. R. Ferguson, K. F. Hansen
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 189-205
Technical Paper | doi.org/10.13182/NSE73-A26594
On Autocatalysis During Fast Reactor Disassembly
Jay E. Boudreau, R. C. Erdmann
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 206-222
Technical Paper | doi.org/10.13182/NSE73-A26595
Experimental Fast-Neutron Albedo from Plane Scatterers
Y. Segal, U. German, A. Notea
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 223-234
Technical Note | doi.org/10.13182/NSE73-A26596
Measurement of the Neutron Total Cross Sections of Zircaloy-2, Zirconium-90, and Carbon between 0.4 and 2.4 MeV
R. W. Stooksberry, J. H. Anderson
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 235-238
Technical Note | doi.org/10.13182/NSE73-A26597
The Sensitivity of Neutron Transport Calculations to Nonelastic Neutron Angular Distributions
Ernest F. Plechaty
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 239-242
Technical Note | doi.org/10.13182/NSE73-A26598
Evaluation of the Second-Order Perturbation Terms by the Generalized Perturbation Method
Yasushi Seki
Nuclear Science and Engineering | Volume 51 | Number 2 | June 1973 | Pages 243-251
Technical Note | doi.org/10.13182/NSE51-243
Space-Dependent Neutron Noise Spectra in Bare and D2O-Reflected Reactor Lattices
C. O. Thomas, Jr., S. H. Hanauer, N. P. Baumann
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 253-261
Technical Paper | doi.org/10.13182/NSE73-A26603
Measurements of Spatially Independent Reactivity in Pulsed-Neutron Experiments
F. C. Difilippo, N. B. Pieroni, J. C. Viez
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 262-271
Technical Paper | doi.org/10.13182/NSE73-A26604
Multiple Reaction Correction to Neutron Reaction Cross Sections
Joseph J. Devaney
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 272-277
Technical Paper | doi.org/10.13182/NSE73-A26605
Measurements and Calculations of the Neutron Spectra from Iron Bombarded with 14-MeV Neutrons
L. F. Hansen, J. D. Anderson, P. S. Brown, R. J. Howerton, J. L. Kammerdiener, C. M. Logan, E. F. Plechaty, C. Wong
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 278-295
Technical Paper | doi.org/10.13182/NSE73-A26606
Gamma-Ray Production Cross Sections of Neutron-Induced Uranium-238 Reactions
Hiroshi Takahashi
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 296-315
Technical Paper | doi.org/10.13182/NSE73-A26607
Optimum Eigenvalue Bounds for Neutron Diffusion and Transport Theory
David B. Reister
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 316-323
Technical Paper | doi.org/10.13182/NSE73-A26608
Inner Iteration Error in the SN Algorithm
Gerald L. Atkinson, William Kerr, James J. Duderstadt
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 324-330
Technical Paper | doi.org/10.13182/NSE73-A26609
Multigroup Diffusion Coefficients from Transport Theory
O. J. Sheaks, L. Harold Sullivan, Raymond L. Murray
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 331-335
Technical Note | doi.org/10.13182/NSE73-A26610
Effect of Shape of the Assembly on the Decay Constant in Pulsed-Neutron Experiments
Feroz Ahmed, Rajesh Mohan
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 335-337
Technical Note | doi.org/10.13182/NSE73-A26611
Total Gamma-Ray Cross Sections
M. V. Ramana Murty, K. Parthasaradhi, S. Ramamurty
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 337-339
Technical Note | doi.org/10.13182/NSE73-A26612
A Class of Second-Order Approximate Formulations of Deep Penetration Radiation Transport Problems
S. A. W. Gerstl, W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 51 | Number 3 | July 1973 | Pages 339-343
Technical Note | doi.org/10.13182/NSE73-A26613
The Stability of Power Reactors Subject to Stochastic Macroscopic Parameter Variation
G. A. Krist, C. G. Poncelet
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 347-375
Technical Paper | doi.org/10.13182/NSE73-A23272
Fission Cross Section of Californium-249
M. G. Silbert
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 376-384
Technical Paper | doi.org/10.13182/NSE73-A23273
Measurement of the Uranium-238 Capture Cross Section for Incident Neutron Energies up to 100 keV
G. de Saussure, E. G. Silver, R. B. Perez, R. Ingle, H. Weaver
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 385-404
Technical Paper | doi.org/10.13182/NSE73-1
Thermal-Neutron Spectrum Indexes in D2O-Moderated Uranium and Uranium-Plutonium Fuel Elements in the Temperature Range from 20 to 200°C
S. Guardini, N. Schiavone, S. Tassan
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 405-414
Technical Paper | doi.org/10.13182/NSE73-A23275
Heterogeneity Effects in ZPPR Assembly 2—A Plutonium-Fueled Demonstration Fast Reactor Study
W. G. Davey, P. I. Amundson, P. J. Collins, R. G. Palmer
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 415-440
Technical Paper | doi.org/10.13182/NSE73-A23276
Neutron Resonance Absorption in Heterogeneous Fast Reactor Assemblies
Yukio Ishiguro
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 441-455
Technical Paper | doi.org/10.13182/NSE73-A23277
Finite Element Methods for Reactor Analysis
C. M. Kang, K. F. Hansen
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 456-495
Technical Paper | doi.org/10.13182/NSE73-A23278
Neutron Capture Gamma-Ray Yields in Iron
J. E. White, C. Y. Fu, K. J. Yost
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 496-508
Technical Note | doi.org/10.13182/NSE73-A23279
Elastic Scattering Probability Functions in Arbitrary Coordinate Systems
B. R. Wienke
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 508-511
Technical Note | doi.org/10.13182/NSE73-A23280
Application of Intermediate Treatment of Resonance Absorption to Heterogeneous Fast Reactor Assembly
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 512-514
Technical Note | doi.org/10.13182/NSE73-A23281