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
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Aug 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
October 2024
Nuclear Technology
Fusion Science and Technology
August 2024
Latest News
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
Jump to:
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