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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
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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A Three-Dimensional Stochastic Gamma-Ray Transport Method for Shielding Calculations
Arsalan Razani, H. E. Hungerford
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE71-A22330
Monte Carlo Calculation of the Effect of Subterranean Perturbations on Reflected X Rays
W. A. Coleman
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 12-21
Technical Paper | doi.org/10.13182/NSE71-A22331
Integral Reaction Rate Determinations—Part I. Tailored Reactor Spectrum Preparation and Measurement
E. Linn Draper, Jr.
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 22-30
Technical Paper | doi.org/10.13182/NSE71-A22332
Integral Reaction Rate Determinations—Part II: Fission Rate Measurements
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 31-41
Technical Paper | doi.org/10.13182/NSE71-A22333
Predictions of the Energy Dependence of the Average Yield of Neutrons Per Fission of Isotopes of Thorium, Uranium, and Plutonium
Robert J. Howerton
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 42-52
Technical Paper | doi.org/10.13182/NSE71-A22334
Spectra of Fast Neutrons from Water Pulsed with 14-MeV Neutrons
Marion L. Stelts, John D. Anderson, Luisa F. Hansen, Ernest F. Plechaty, Calvin Wong
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 53-60
Technical Paper | doi.org/10.13182/NSE71-A22335
Neutron Flux in Cells of Finite, Square Lattices
T. Auerbach
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 61-75
Technical Paper | doi.org/10.13182/NSE71-A22336
Criticality Measurements on Uranium Metal Spheres Immersed in Uranium Solution
D. C. Hunt, Robert E. Rothe
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 76-87
Technical Paper | doi.org/10.13182/NSE71-A22337
Optimal Control Rod Programming of Light Water Reactors in Equilibrium Fuel Cycle
Hiroshi Motoda
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 88-111
Technical Paper | doi.org/10.13182/NSE71-A22338
Application of Linear Programming to Refueling Optimization for Light Water Moderated Power Reactors
Atsuyuki Suzuki, Ryohei Kiyose
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 112-130
Technical Paper | doi.org/10.13182/NSE71-A22339
Measurement of the Effect of Twisted Tapes on the Forced-Convection Heat Transfer and Burnout in Heat Exchangers
R. Brevi, M. Cumo, A. Palmieri, D. Pitimada
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 131-139
Technical Paper | doi.org/10.13182/NSE71-A22340
Optimal Strategies in Reactor System Economics
Paul Nelson, Jr., Gale Young
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 140-147
Technical Note | doi.org/10.13182/NSE71-A22341
New Method for Measurement of the Effective Fraction of Delayed Neutrons from Fission
J. T. Mihalczo
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 147-148
Technical Note | doi.org/10.13182/NSE71-A22342
Measurements of the Total Neutron Cross Section of Praseodymium Between 1 and 18 MeV
M. Enayetullah, N. Ameen, N. Islam, M. Hussain, S. Husain, E. Islam
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 148-150
Technical Note | doi.org/10.13182/NSE71-A22343
Synthesis of Fast Reactor Neutron Energy Spectra
P. A. Ombrellaro, M. A. Snider
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 150-159
Technical Note | doi.org/10.13182/NSE71-A22344
Regional-Dependent Reactor Kinetics
David S. Gooden, T. F. Parkinson
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 169-178
Technical Paper | doi.org/10.13182/NSE71-A22351
Noise and Transient Kinetics Experiments and Calculations for Loosely Coupled Cores
R. A. Rydin, J. A. Burke, W. E. Moore, K. W. Seemann
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 179-196
Technical Paper | doi.org/10.13182/NSE71-A22352
Optimum Bounds for Space-Time Reactor Problems Using Linear Programming
David B. Reister
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 197-202
Technical Paper | doi.org/10.13182/NSE71-A22353
Effect of Transverse Dimensions on the Diffusion Length of Neutrons in Crystalline Moderator Assemblies
Feroz Ahmed, L. S. Kothari, Ashok Kumar
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 203-213
Technical Paper | doi.org/10.13182/NSE71-A22354
Pulsed-Neutron Diffusion Parameters in Mixtures of Heavy and Light Water and Ice
George N. Salaita, Andrew Robeson
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 214-222
Technical Paper | doi.org/10.13182/NSE71-A22355
The Temperature Dependence of Neutron Inelastic Scattering from Water
L. J. Esch, M. L. Yeater, W. E. Moore, K. W. Seemann
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 223-235
Technical Paper | doi.org/10.13182/NSE71-A22356
Measured Neutron Spectra in a Number of Uranium- and Plutonium-Fueled Reactor Assemblies
T. J. Yule, E. F. Bennett
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 236-243
Technical Paper | doi.org/10.13182/NSE71-A22357
Measurements of Thermal-Neutron Spectra in Plutonium Nitrate Solutions
J. M. Neill, J. C. Young, C. A. Preskitt, G. D. Trimble, R. C. Lloyd, C. L. Brown
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 244-254
Technical Paper | doi.org/10.13182/NSE71-A22358
Statistical Model Calculations of Iron-56 Neutron Cross Sections
S. D. Bloom, J. M. Green, H. W. Hubbard, S. A. Moszkowski
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 255-265
Technical Paper | doi.org/10.13182/NSE71-A22359
Parametric Fit of the Neutron Cross Section of Holmium
Thomas E. Stephenson, Alberto M. Ferrer
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 266-273
Technical Paper | doi.org/10.13182/NSE71-A22360
Application of Linear Programming to In-Core Fuel Management Optimization in Light Water Reactors
T. O. Sauar
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 274-283
Technical Paper | doi.org/10.13182/NSE71-A22361
Turbulent-Flow Heat Transfer for In-Line Flow Through Unbaffled Rod Bundles: Molecular Conduction Only
O. E. Dwyer, H. C. Berry
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 284-303
Technical Paper | doi.org/10.13182/NSE71-A22362
Advances in the Generalized Perturbation Theory
G. P. Cecchini, M. Salvatores
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 304-309
Technical Note | doi.org/10.13182/NSE46-304
New Difference Schemes for the Neutron Transport Equation
William H. Reed
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 309-314
Technical Note | doi.org/10.13182/NSE46-309
Neutron Absorption Cross Sections for Zirconium-94 and Zirconium-96
R. H. Fulmer, D. P. Stricos, T. F. Ruane
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 314-317
Technical Note | doi.org/10.13182/NSE71-A22365
Positive Difference Schemes in Neutron Spectral Codes
Teresa Kulikowska
Nuclear Science and Engineering | Volume 46 | Number 2 | November 1971 | Pages 317-320
Technical Note | doi.org/10.13182/NSE71-A22366
Plasma Energy Deposition from Nuclear Elastic Scattering
Joseph J. Devaney, Myron L. Stein
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 323-333
Technical Paper | doi.org/10.13182/NSE71-A22370
The Effect of the Ground on the Steady-State and Time-Dependent Transport of Neutrons and Secondary Gamma Rays in the Atmosphere
E.A. Straker
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 334-355
Technical Paper | doi.org/10.13182/NSE71-A22371
Fast Neutron Total and Scattering Cross Sections of Uranium-238
P. Lambropoulos
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 356-365
Technical Paper | doi.org/10.13182/NSE71-A22372
A New Solution of the Point Kinetics Equations
J. A. W. da Nóbrega
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 366-375
Technical Paper | doi.org/10.13182/NSE71-A22373
Evaluation of Neutron Spectral Effects in a Plutonium-Fueled Lattice by Foil Activation
F. V. Orestano, F. Pistella
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 376-384
Technical Paper | doi.org/10.13182/NSE71-A22374
Application of Nonlinear Programming to the Optimal Control of Point Model Nuclear Reactors
G. F. Malan, B. V. Koen
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 385-393
Technical Paper | doi.org/10.13182/NSE71-A22375
Heated Laminar Gas Flow in Annuli with Temperature-Dependent Transport Properties
R. W. Shumway, D. M. McEligot
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 394-407
Technical Paper | doi.org/10.13182/NSE71-A22376
Dynamic Effects in Radiation Diagnosis of Fluctuating Voids
A. A. Harms, C. F. Forrest
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 408-413
Technical Paper | doi.org/10.13182/NSE71-A22377
Fission Temperatures as a Function of the Average Number of Neutrons from Fission
R. J. Howerton, R. J. Doyas
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 414-416
Technical Note | doi.org/10.13182/NSE71-A22378
Neutron Diffusion from a Fast Point Source in Aqueous Absorbing Solutions
Dong H. Nguyen, Marshall T. Slayton, John A. Frew
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 416-421
Technical Note | doi.org/10.13182/NSE71-A22379
Evaluation of Space-Energy Factorization for Two-Dimensional Diffusion Theory Problems in the Liquid Metal Fast Breeder Reactor
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 421-425
Technical Note | doi.org/10.13182/NSE71-A22380
Roots and Coefficients from the Integral Solution of the Reactor Kinetic Equations Applicable to Uranium-235 Fueled, Heavy Water Moderated Reactors
Joseph S. Crudele, Richard A. Danofsky
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 425-427
Technical Note | doi.org/10.13182/NSE71-A22381
Calculated Thermal (n, α) Cross Section for Nickel-59
G. J. Kirouac
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 427-428
Technical Note | doi.org/10.13182/NSE71-A22382
On a Possible Resolution of the Nitrogen Nonelastic Neutron Cross-Section Discrepancy Below 9 MeV
F. G. Perey, W. E. Kinney
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 428-431
Technical Note | doi.org/10.13182/NSE71-A22383
Critical Heat Fluxes of Full Flux Shapes from Partial Flux Shapes
R. H. Wilson, G. O. Geissler
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 431-436
Technical Note | doi.org/10.13182/NSE71-A22384
