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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.
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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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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.
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Initial Voiding Experiments with Sodium Under Liquid-Metal Fast Breeder Reactor Conditions
D. M. France, R. D. Carlson, R. R. Rohde, G. T. Charmoli
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 1-10
Technical Paper | doi.org/10.13182/NSE74-A23959
A Kinetic Theory for the Annealing of Radiation Damage in Germanium
W. Maurice Pritchard, James L. Reid
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 11-16
Technical Paper | doi.org/10.13182/NSE74-A23960
Improved Activation Measurements of (n, γ) Cross Section for 14.6-MeV Neutrons
F. Rigaud, M. G. Desthuilliers, G. Y. Petit, J. L. Irigaray, G. Longo, F. Saporetti
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 17-23
Technical Paper | doi.org/10.13182/NSE55-17
Cross-Section Measurement of Plutonium-236 Formation in Plutonium-238 by 237Np(n, 2n)Reactions
C. K. Paulson, E. J. Hennelly
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 24-27
Technical Paper | doi.org/10.13182/NSE74-A23962
Spectrum of Delayed Neutrons from the Thermal-Neutron Fission of Uranium-235
W. Robert Sloan, Gene L. Woodruff
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 28-40
Technical Paper | doi.org/10.13182/NSE74-A23963
Angular Distribution Measurements of Secondary-Particle Fluxes with Spallation Detectors and Comparisons to Hadron Cascade Calculations
J. T. Routti
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 41-50
Technical Paper | doi.org/10.13182/NSE74-A23964
Criticality of Plutonium-Uranium Mixtures Containing 5 to 8 wt% Plutonium
R. C. Lloyd, S. R. Bierman, E. D. Clayton
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 51-57
Technical Paper | doi.org/10.13182/NSE74-A23965
Critical Experiments to Measure the Neutron Poisoning Effects of Copper and Copper-Cadmium Plates
S. R. Bierman, E. D. Clayton
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 58-66
Technical Paper | doi.org/10.13182/NSE74-A23966
Calculation of Electron Transport in a Slab
O. B. Evdokimov, A. P. Yalovets
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 67-75
Technical Paper | doi.org/10.13182/NSE74-A23967
Analytic X-Ray Transport Theory for Numerical Computation
Randall K. Cole, Jr.
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 76-84
Technical Paper | doi.org/10.13182/NSE74-A23968
Lifetime-Averaged Cross Sections for X-Ray Transport Calculations
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 85-88
Technical Paper | doi.org/10.13182/NSE74-A23969
Calculations of a Fast-Neutron Shielding Experiment for Evaluating Approximate Shielding Design Methods
C. R. Adkins
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 89-96
Technical Note | doi.org/10.13182/NSE74-A23970
Evaluation of Integrals by Differentiation with Application to Collision Methods
G. Bitelli, A. Turrin
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 96-97
Technical Note | doi.org/10.13182/NSE74-A23971
An Accelerated Spectral Synthesis Technique
William G. Price, Jr., James J. Duderstadt
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 98-102
Technical Note | doi.org/10.13182/NSE74-A23972
Comparative Analysis of Neutron Data Files as a Sensitivity Study
M. Segev, S. Yiftah, Y. Gur, L. Gitter
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 103-104
Technical Note | doi.org/10.13182/NSE74-A23973
Measurement of Anisotropic Neutron Diffusion Coefficients in Square Lattices of Aluminum in Light Water by the Pulsed Neutron Method
Yoshihiko Kaneko, Fujiyoshi Akino, Yoshiro Suzuoki, Kenji Kitadate, Ryosuke Kurokawa,Kinji Koyama
Nuclear Science and Engineering | Volume 55 | Number 1 | September 1974 | Pages 105-116
Technical Note | doi.org/10.13182/NSE74-A23974
Space-Time Nuclear Reactor Analysis by Temporal Transformation
W. J. Garland, A. A. Harms, J. Vlachopoulos
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 119-128
Technical Paper | doi.org/10.13182/NSE74-A28202
Measurements at the Critical Facility for the In-Core Thermionic Reactor and Comparison with Calculations
M. Bloser, N. Kirch, F. J. Krings, A. Naseband, N. Paul
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 129-146
Technical Paper | doi.org/10.13182/NSE74-A28203
Radiation-Transport Cross-Section Sensitivity Analysis— A General Approach Illustrated for a Thermonuclear Source in Air
D. E. Bartine, E. M. Oblow, F. R. Mynatt
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 147-167
Technical Paper | doi.org/10.13182/NSE74-A28204
Gamma-Ray-Production Cross Sections for the 56Fe(n,n’y) Reaction from 2.5- to 14.1-MeV Neutron Energies
J. Lachkar, J. Sigaud, Y. Patin, G. Haouat
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 168-187
Technical Paper | doi.org/10.13182/NSE74-A28205
Prompt-Neutron Yield from the Spontaneous Fission of Californium-252
J. W. Boldeman
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 188-202
Technical Paper | doi.org/10.13182/NSE74-A28206
Measurement of the Fission Cross Section of Uranium-235 for Incident Neutrons with Energies Between 2 and 100 keV
R. B. Perez, G. de Saussure, E. G. Silver, R. W. Ingle, H. Weaver
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 203-218
Technical Paper | doi.org/10.13182/NSE74-A28207
Optimum Active-Inactive Times in Supervised Protective Systems for Nuclear Reactors
J. M. Kontoleon, Nadia Kontoleon, N. G. Chrysochoides
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 219-224
Technical Paper | doi.org/10.13182/NSE74-A28208
Transport Calculations of the Neutron Escape Probability
A. M. Melandri, F. Premuda, G. P. Prelati
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 225-233
Technical Note | doi.org/10.13182/NSE74-A28209
Half-Range Orthogonality Theorem for Thermal-Neutron Transport
Yuji Ishiguro
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 233-234
Technical Note | doi.org/10.13182/NSE74-A28210
On the Randomness of a Neutron’s Kinetic Energy as It Slows Down by Elastic Collisions in an Infinite Medium
C. S. Barnett
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 234-242
Technical Note | doi.org/10.13182/NSE74-A28211
Incomplete Neutron Thermalization in Light Water Ice at 77, 21, and 4 K
G. S. Gangwani, L. S. Kothari
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 242-243
Technical Note | doi.org/10.13182/NSE74-A28212
Cross Sections of Aluminum and Iron Averaged Over the Californium-252 Fission Neutron Spectrum
W. G. Alberts, M. Matzke
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 243-244
Technical Note | doi.org/10.13182/NSE74-A28213
Reexamination of the Value for the Minimum Critical Concentration of Plutonuim -239 in Water
C. R. Richey
Nuclear Science and Engineering | Volume 55 | Number 2 | October 1974 | Pages 244-247
Technical Note | doi.org/10.13182/NSE74-A28214
Coolant Flow and Reactivity Oscillations
Y. S. Lu
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 249-255
Technical Paper | doi.org/10.13182/NSE74-A23451
A Comparative Study of Several Fusion Reactor Blanket Designs
M. A. Abdou, Robert W. Conn
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 256-266
Technical Paper | doi.org/10.13182/NSE74-A23452
Cross-Section Requirements for Charged-Particle Fusion Reactors: The 6Li(p,3He)α Reaction
C. R. Gould, R. O. Nelson, J. R. Williams, J. R. Boyce
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 267-272
Technical Paper | doi.org/10.13182/NSE74-A23453
The Neutron Total Cross Section of Americium-243
O. D. Simpson, F. B. Simpson, J. A. Harvey, G. G. Slaughter, R. W. Benjamin, C. E. Ahlfeld
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 273-279
Technical Paper | doi.org/10.13182/NSE74-A23454
The Role of Integral Data in Neutron Cross-Section Evaluation
A. Pazy, G. Rakavy, I. Reiss, J. J. Wagschal, Atara Ya’ari, Y. Yeivin
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 280-295
Technical Paper | doi.org/10.13182/NSE55-280
Binary Signals Constructed from Walsh Sequences for Reactor Dynamics Measurements
R. W. Albrecht, S. A. Wright
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 296-306
Technical Paper | doi.org/10.13182/NSE74-A23456
The Time-Dependent Nuclear Reactor with Feedback
Dong H. Nguyen
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 307-319
Technical Paper | doi.org/10.13182/NSE74-A23457
Solution of Two-Dimensional Diffusion Equation by the Finite Fourier Transformation
Keisuke Kobayashi, Nobuo Ohtani, Jungchung Jung
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 320-328
Technical Paper | doi.org/10.13182/NSE74-A23458
A New Procedure for the Determination of Neutron Multigroup Transfer Matrices
C. R. Weisbin, P. D. Soran, J. S. Hendricks
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 329-341
Technical Paper | doi.org/10.13182/NSE74-A23459
Radiation Converter Plate Design
M. S. Ash, G. Yanow
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 342-344
Technical Note | doi.org/10.13182/NSE74-A23460
Measurements and Calculations of the Neutron Spectra Emitted from Concrete Spheres Bombarded with 14-MeV Neutrons
L. F. Hansen, J. D. Anderson, R. J. Doyas, R. J. Howerton, T. Komoto, C. M. Logan, C. Wong, J. L. Kammerdiener
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 345-348
Technical Note | doi.org/10.13182/NSE74-A23461
Multiregion Equivalence Relation for Resonance Heterogeneity Effects
Yukio Ishiguro
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 349-351
Technical Note | doi.org/10.13182/NSE74-A23462
A Simplified Derivation of the Poincaré-Bertrand Formula
L. C. Baird, P. F. Zweifel
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 351-353
Technical Note | doi.org/10.13182/NSE74-A23463
Transport and Diffusion Equations in Toroidal Geometry
G. C. Pomraning, C. A. Stevens
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 359-367
Technical Paper | doi.org/10.13182/NSE74-A23469
Investigation of the Space- and Energy-Dependent Coherence Function in Zero-Power Coupled-Core Reactors
D. D. Ebert, J. D. Clement, W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 368-379
Technical Paper | doi.org/10.13182/NSE74-A23470
Interpretation of Coherence Function Measurements in Zero-Power Coupled-Core Reactors
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 380-386
Technical Paper | doi.org/10.13182/NSE74-A23471
Application of the Probability Table Method to Multigroup Calculations of Neutron Transport
Dermott E. Cullen
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 387-400
Technical Paper | doi.org/10.13182/NSE74-3
Measurement and Analysis of Parameters in Tight 232Th-235U and 232Th-233U Lattices Moderated with Heavy Water
J. Hardy, Jr., J. J. Volpe, D. Klein
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 401-417
Technical Paper | doi.org/10.13182/NSE74-2
Semiclassical Description of Fast-Neutron Cross Sections
I. Angeli, J. Csikai, P. Nagy
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 418-426
Technical Paper | doi.org/10.13182/NSE74-A23474
Cross Sections of Uranium-235 and Plutonium-239 for Neutrons Producing Gamma Rays
Darrell M. Drake
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 427-439
Technical Paper | doi.org/10.13182/NSE74-A23475
Neutron Total Cross Section of Curium-248
R. W. Benjamin, C. E. Ahlfeld, J. A. Harvey, N. W. Hill
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 440-449
Technical Paper | doi.org/10.13182/NSE74-A23476
Half-Lives of Some Cosmogenic Radionuclides: 7Be, 46Sc, 54Mn, 56Co, and 65Zn
Philip J. Cressy, Jr.
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 450-451
Technical Paper | doi.org/10.13182/NSE74-A23477
High-Temperature Properties of Sodium for Safety Studies of Liquid-Metal Fast Breeder Reactors
A. Padilla, Jr.
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 452-461
Technical Paper | doi.org/10.13182/NSE74-A23478
Thermal Fragmentation—A Gas Release Phenomenon
Michael Epstein
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 462-467
Technical Paper | doi.org/10.13182/NSE74-4
Higher Order Variational Principles and Padé Approximants for Linear Functionals
Robert W. Conn
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 468-470
Technical Note | doi.org/10.13182/NSE74-A23480
An Inherent Noise Analysis Investigation on the Experimental Breeder Reactor II
David D. Ebert
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 470-476
Technical Note | doi.org/10.13182/NSE74-A23481
Neutron Moderation in Fast Reactors in the Presence of Wide Scattering Resonances: Analysis of Methods
G. Palmiotti, M. Salvatores
Nuclear Science and Engineering | Volume 55 | Number 4 | December 1974 | Pages 476-480
Technical Note | doi.org/10.13182/NSE74-A23482