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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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Latest News
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 Physical Basis for Two-Phase Pressure Gradient and Critical Flow Calculations
P. E. Tremblay, D. G. Andrews
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE71-A18899
Influence of Coated-Particle Structure in Thermal-Neutron-Spectrum Energy Range
U. Hansen, E. Teuchert
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 12-17
Technical Paper | doi.org/10.13182/NSE44-12
An Analysis of Bare and Reflected Metal Critical Assemblies Using ENDF/B Data
Hans Ludewig
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 18-26
Technical Paper | doi.org/10.13182/NSE71-A18901
Solutions of the Diffusion Equation by the Spectral-Synthesis Method
Paul G. Lorenzini, Alan H. Robinson
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 27-36
Technical Paper | doi.org/10.13182/NSE71-A18902
A Simplified, Coarse-Mesh, Three-Dimensional Diffusion Scheme for Calculating the Gross Power Distribution in a Boiling Water Reactor
S. Børresen
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 37-43
Technical Paper | doi.org/10.13182/NSE71-A18903
An Altered Diffusion Theory Based on the Double P-0 Approximation for All Geometries
Stefano L. Paveri-Fontana, Harvey Amster
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 44-57
Technical Paper | doi.org/10.13182/NSE71-A18904
The Tensor Form of the Neutron-Transport Equation with Application to Finite Differencing
D. W. Drawbaugh
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 58-65
Technical Paper | doi.org/10.13182/NSE71-A18905
Reactor Kinetic Parameters of Lattices of Plutonium and Uranium in Water
V. O. Uotinen, J. H. Lauby, W. P. Stinson, S. R. Dwivedi
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 66-71
Technical Paper | doi.org/10.13182/NSE71-A18906
Improved Spatial Differencing for the Solution of Space-Time Problems Arising from the Movement of Reactor Materials
J. B. Yasinsky, L. R. Foulke
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 72-85
Technical Paper | doi.org/10.13182/NSE71-A18907
On the Determination of Stability Domains in Nonlinear Point Reactor Dynamics
Richard Ziskind, William E. Kastenberg
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 86-94
Technical Paper | doi.org/10.13182/NSE71-A18908
Tests of Evaluated Beryllium (n, 2n) Cross Sections by Analysis of 1.4-eV Flux in Water for an Americium-Beryllium Source Enclosed in Beryllium Spheres
Roger L. Alexander, Daniel Fieno, C. Hubbard Ford
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 95-102
Technical Note | doi.org/10.13182/NSE71-A18909
Pair-Production Cross Sections at 2.75 MeV
H. F. Atwater
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 102-104
Technical Note | doi.org/10.13182/NSE71-A18910
An Approximate High-Energy Alpha-Particle Nucleus Collision Model
T. A. Gabriel, R. T. Santoro, R. G. Alsmiller, Jr.
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 104-110
Technical Note | doi.org/10.13182/NSE71-A18911
Subcritical Reactivity from Reactor Noise
Andreas Szeless, Lawrence Ruby
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Pages 110-112
Technical Note | doi.org/10.13182/NSE71-A18912
Comment on Subcritical Reactivity from Reactor Noise
Robert W. Albrecht
Nuclear Science and Engineering | Volume 44 | Number 1 | April 1971 | Page 112
Technical Note | doi.org/10.13182/NSE71-A18913
Maximizing the Average Fuel Burnup Over Entire Core: A Poison Management Optimization Problem for Multizone Light-Water Reactor Cores
Atsuyuki Suzuki, Ryohei Kiyose
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 121-134
Technical Paper | doi.org/10.13182/NSE71-A19662
An Integrated Model for Analyzing Disruptive Accidents in Fast Reactors
William T. Sha, Alan E. Waltar
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 135-156
Technical Paper | doi.org/10.13182/NSE71-A19663
Calculations of Weapon Radiation Doses in Single-Compartment Aboveground Concrete Structures
L. G. Mooney
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 157-172
Technical Paper | doi.org/10.13182/NSE71-A19664
Measurement of the Delayed-Neutron Fractions for Thermal Fission of Uranium-235, Plutonium-239, and Uranium-233
John F. Conant, Philip F. Palmedo
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 173-179
Technical Paper | doi.org/10.13182/NSE71-A19665
Epithermal Measurements of Capture and Fission Resonance Integrals in 235U, 233U, 239Pu, and 241Pu
H. M. Eiland, L. J. Esch, F. Feiner, J. L. Mewherter
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 180-189
Technical Paper | doi.org/10.13182/NSE71-A19666
Neutron Yield from the (α, n) Reaction in the Isotope Oxygen-18
Mojtaba Taherzadeh
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 190-193
Technical Paper | doi.org/10.13182/NSE71-A19667
The Effect of Anisotropic Scattering Upon the Elastic Moderation of Fast Neutrons
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 194-203
Technical Paper | doi.org/10.13182/NSE71-A19668
Synthesis of Fast Reactor Space-Energy Neutron Fluxes
P. A. Ombrellaro
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 204-220
Technical Paper | doi.org/10.13182/NSE71-A19669
Measurements and Calculations of Neutron Migration and its Anisotropy in Lattices of Fuel Rods and Liquid Coolant
D. R. Harris, J. A. Mitchell
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 221-238
Technical Paper | doi.org/10.13182/NSE71-A19670
Application of Alternating-Direction Implicit Methods to the Space-Dependent Kinetics Equations
A. L. Wight, K. F. Hansen, D. R. Ferguson
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 239-251
Technical Paper | doi.org/10.13182/NSE71-A19671
Neutron Streaming Through Ducts—Analysis of Experimental Results
Y. T. Song, C. M. Huddleston, A. B. Chilton
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 252-261
Technical Note | doi.org/10.13182/NSE71-A19672
An Improved Method for Calculating Foil Perturbation Effects
Darrell F. Newman
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 261-266
Technical Note | doi.org/10.13182/NSE71-A19673
Values of Eta of Uranium-233, Uranium-235, and Plutonium-239 from Critical Experiments and Reactivity Measurements
D. W. Magnuson
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 266-267
Technical Note | doi.org/10.13182/NSE71-A19674
Optimization of Nuclear Systems by Geometric Programming
G. D. Bouchey, C. S. Beightler, B. V. Koen
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 267-272
Technical Note | doi.org/10.13182/NSE71-A19675
Some Comments on Perturbation Theory
D. S. Selengut
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 272-275
Technical Note | doi.org/10.13182/NSE71-A19676
An Analytical and Experimental Investigation of the Vibration of Cylindrical Reactor Fuel Elements in Two-Phase Parallel Flow
D. J. Gorman
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 277-290
Technical Paper | doi.org/10.13182/NSE71-A20161
A Generalized Local Boiling Void Model for Light-Water Reactor System
William T. Sha
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 291-300
Technical Paper | doi.org/10.13182/NSE71-A20162
Dynamic Stability of Cylindrical Shells Subjected to Sonic Waves Due to a Loss-of-Coolant Reactor Accident
George J. Bohm, Elmar A. Steck
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 301-309
Technical Paper | doi.org/10.13182/NSE71-A20163
Carbon Loss from Graphite Cylinders Exposed to Steam for Short Times
M. Necati Özişik, H. J. de Nordwall
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 310-319
Technical Paper | doi.org/10.13182/NSE71-A20164
A Study of Coolant Transients During a Rapid Fission Gas Release in a Fast Reactor Subassembly
T. C. Chawla, B. M. Hoglund
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 320-344
Technical Paper | doi.org/10.13182/NSE71-A20165
An Evaluation of the Number of Neutrons Per Fission for the Principal Plutonium, Uranium, and Thorium Isotopes
W. G. Davey
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 345-371
Technical Paper | doi.org/10.13182/NSE71-A20166
Effect of Moderation on Reaction Cross-Section Measurements
Melvin M. Levine
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 372-375
Technical Paper | doi.org/10.13182/NSE71-A20167
Fast Neutron Penetration in Paraffin and Lithium Hydride
A. E. Profio, R. J. Cerbone, D. L. Huffman
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 376-387
Technical Paper | doi.org/10.13182/NSE71-A20168
The Measurement of Flux Fine Structure in Plate Fast Reactor Cells of Finite Size
Philip F. Palmedo, Henry H. Windsor
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 388-397
Technical Paper | doi.org/10.13182/NSE71-A20169
An Analysis of Flux Fine Structure in One-Dimensional Fast Reactor Cells
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 398-405
Technical Paper | doi.org/10.13182/NSE71-A20170
Bounded Estimators for Flux at a Point in Monte Carlo
Herbert A. Steinberg, Malvin H. Kalos
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 406-412
Technical Paper | doi.org/10.13182/NSE71-A20171
The Reactivity Effect of Replacing a Water Reflector with Lead
G. Klotzkin, R. F. Valentine, C. A. Flanagan, J. C. Stachew
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 413-422
Technical Paper | doi.org/10.13182/NSE71-A20172
The SPN-PL Method for Neutron Transport in Homogeneous Slabs with Anisotropic Scattering
H. Kschwendt
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 423-434
Technical Paper | doi.org/10.13182/NSE71-A20173
The Influence of Power Flattening on Hot Channel Factors
A. Amendola
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 435-437
Technical Note | doi.org/10.13182/NSE71-A20174
Thick Target Yields for the 9Be(α, n) Reaction
M. E. Anderson, M. R. Hertz
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 437-439
Technical Note | doi.org/10.13182/NSE71-A20175
Note on the Prompt-Fission-Neutron Spectra of Uranium-235 and Plutonium-239
A. B. Smith
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 439-442
Technical Note | doi.org/10.13182/NSE71-A20176
Approximate Treatments of the Effect of Anisotropy on Elastic Neutron Moderation
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 442-444
Technical Note | doi.org/10.13182/NSE71-A20177
Slowing Down and Heating Up of Neutrons in Graphite at Low Temperatures
Vidya Bhushan, S. K. Trikha
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 444-447
Technical Note | doi.org/10.13182/NSE71-A20178
Adjoint Spectra for Calculating Thermal Group Constants
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 447-449
Technical Note | doi.org/10.13182/NSE71-A20179
A Theorem Concerning Reflection and Transmission from a Nonabsorbing Slab
Raphael Aronson
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 449-450
Technical Note | doi.org/10.13182/NSE71-A20180
Experimental Determination of the Perturbation Denominator in Fast Critical Assemblies
W. C. Redman, M. M. Bretscher
Nuclear Science and Engineering | Volume 44 | Number 3 | June 1971 | Pages 450-453
Technical Note | doi.org/10.13182/NSE71-A20181
