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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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
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Burnup Optimization of Continuous Scattered Refueling
Hiroshi Motoda
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE70-A20357
A Numerical Method for the Solution of Three-Dimensional Neutron-Transport Problems
M. R. Wagner, D. A. Sargis, S. C. Cohen
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 14-21
Technical Paper | doi.org/10.13182/NSE70-A20358
Extrapolation Distances and Diffusion Parameters via Pulsed-Neutron Analysis
J. Dorning
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 22-28
Technical Paper | doi.org/10.13182/NSE70-A20359
An Analytic Representation of Fast-Reactor Neutron-Energy Spectra
H. Nissimov, Y. Reiss, Y. Yeivin
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 29-36
Technical Paper | doi.org/10.13182/NSE70-A20360
Estimation of Spatial Distributions of Neutron Captures in Resonance Absorbers
Donald Bogart
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 37-46
Technical Paper | doi.org/10.13182/NSE70-A20361
Calculation of the Photon-Production Spectrum from Proton-Nucleus Collisions in the Energy Range 15 to 150 MeV and Comparison with Experiment
Y. Shima, R. G. Alsmiller, Jr.
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 47-55
Technical Paper | doi.org/10.13182/NSE70-A20362
A Measurement of the Capture-to-Fission Ratio for Plutonium-239
J. B. Czirr, J. S. Lindsey
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 56-62
Technical Paper | doi.org/10.13182/NSE70-A20363
Fast-Neutron Total and Scattering Cross Sections of Bismuth
A. B. Smith, J. F. Whalen, E. Barnard, J. A. M. de Villiers, D. Reitmann
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 63-69
Technical Paper | doi.org/10.13182/NSE70-A20364
The Optimal Allocation of Energy in Industrial and Agro-Industrial Complexes Using Dynamic Programming
G. D. Bouchey, B. V. Koen, C. S. Beightler
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 70-78
Technical Paper | doi.org/10.13182/NSE70-A20365
Two-Phase Critical Flow at Low Qualities Part I: Experimental
Robert E. Henry, Hans K. Fauske, Stuart T. McComas
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 79-91
Technical Paper | doi.org/10.13182/NSE70-A20366
Two-Phase Critical Flow at Low Qualities Part II: Analysis
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 92-98
Technical Paper | doi.org/10.13182/NSE70-A20367
Theoretical Investigations on Sodium Boiling in Fast Reactors
E. G. Schlechtendahl
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 99-114
Technical Paper | doi.org/10.13182/NSE70-A20368
Space-Dependent Dynamic Behavior of Fast Reactors Using the Time-Discontinuous Synthesis Method
G. Kessler
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 115-125
Technical Note | doi.org/10.13182/NSE70-A20369
State Variable Feedback and Series Compensation of Multivariate Systems
Charles R. Slivinsky, Donald G. Schultz, Lynn E. Weaver
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 125-129
Technical Note | doi.org/10.13182/NSE70-A20370
Stochastic Stability of a Reactor with Linear Feedback
Donald J. Dudziak
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 129-132
Technical Note | doi.org/10.13182/NSE70-A20371
Pulsed-Neutron Determination of the Effective Multiplying Constant and Neutron Age to Thermal Energy for a Bare Homogeneous Subcritical Assembly of Enriched-Uranyl-Nitrate Salt
R. H. Chow, S. R. Bierman
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 132-138
Technical Note | doi.org/10.13182/NSE70-A20372
Pulse Neutron Decay in Heavy-Water Spheres
J. Dorning, A. Ginsberg
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 138-140
Technical Note | doi.org/10.13182/NSE70-A20373
Legendre Moments of the Elastic-Scattering Cross Section for S-Wave Neutrons
R. A. Grimesey, W. Serrano, R. A. Dannels
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 140-143
Technical Note | doi.org/10.13182/NSE70-A20374
Derivation of 239Pu Resonance Parameters from Correlation of Experimental Data
R. N. Evatt, B. A. Hutchins
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 143-146
Technical Note | doi.org/10.13182/NSE70-A20375
Effective Capture and Fission Cross Sections for Californium-253
C. E. Bemis, Jr., R. E. Druschel, J. Halperin
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 146-147
Technical Note | doi.org/10.13182/NSE70-A20376
Sensitivity of Secondary Gamma-Ray Dose to Angular Distribution of Gamma Rays from Neutron Inelastic Scattering
E. A. Straker
Nuclear Science and Engineering | Volume 41 | Number 1 | July 1970 | Pages 147-148
Technical Note | doi.org/10.13182/NSE70-A20377
Primary-Recoil Atom Spectra from ENDF/B Data
J. D. Jenkins
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 155-163
Technical Paper | doi.org/10.13182/NSE70-A20703
Neutron Spectrum Measurements in a Homogeneous Erbium System and Erbium Cross Sections
T. Gozani, G. D. Trimble
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 164-176
Technical Paper | doi.org/10.13182/NSE70-A20704
Neutron Fission Cross Sections for 231Th, 233Th, 235U, 237U, 239U, 241Pu, and 243Pu from 0.5 to 2.25 MeV Using (t, pf) Reactions
J. D. Cramer, H. C. Britt
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 177-187
Technical Paper | doi.org/10.13182/NSE70-A20705
Total Neutron Cross Section of Technetium-99 from 0.01 to 1000 eV
T. Watanabe, S. D. Reeder
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 188-192
Technical Paper | doi.org/10.13182/NSE70-A20706
A Unified Model of Deformed Odd-Odd Nuclei for Nuclear Data Generation and Analysis
C. Y. Fu, K. J. Yost
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 193-208
Technical Paper | doi.org/10.13182/NSE70-A20707
Reaction Rates in Representative Plutonium-Recycle Fuel Lattices
J. G. Carver, W. R. Morgan, C. R. Porter, M. A. Robkin
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 209-225
Technical Paper | doi.org/10.13182/NSE70-A20708
Linearly Anisotropic Extensions of Asymptotic Neutron Diffusion Theory
R. J. Doyas, B. L. Koponen
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 226-236
Technical Paper | doi.org/10.13182/NSE70-A20709
Truncation Error Analysis of Finite Difference Approximations to the Transport Equation
Wm. H. Reed, K. D. Lathrop
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 237-248
Technical Paper | doi.org/10.13182/NSE70-A20710
Spectral Synthesis Applied to Fast-Reactor Dynamics
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 249-258
Technical Paper | doi.org/10.13182/NSE70-A20711
Monte Carlo Method for Geometrical Perturbation and its Application to the Pulsed Fast Reactor
Hiroshi Takahashi
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 259-270
Technical Paper | doi.org/10.13182/NSE70-A20712
Hybrid Computer Solution of Thermal Energy Equations in Porous Fuels
W. W. Marr, M. M. El-Wakil
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 271-280
Technical Paper | doi.org/10.13182/NSE70-A20713
Transient Digital Control of a Boiling-Water Reactor Power Plant
W. Ciechanowicz, B. Lazarević
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 281-293
Technical Paper | doi.org/10.13182/NSE70-A20714
An Experimental Investigation of Absorption in the 1.056 eV Resonance of Plutonium-240
Charles J. Hulka, Gene L. Woodruff
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 294-296
Technical Note | doi.org/10.13182/NSE70-A20715
Use of Californium-252 as a Randomly Pulsed Neutron Source for Prompt Neutron Decay Measurements
John T. Mihalczo
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 296-298
Technical Note | doi.org/10.13182/NSE70-A20716
Gozani's Pulsed Neutron Technique with Repeated Recycling of Analyzer Between Bursts
R. H. Chow
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 298-299
Technical Note | doi.org/10.13182/NSE70-A20717
An Implicit Method for Solving the Lumped Parameter Reactor-Kinetics Equations by Repeated Extrapolation
Masayuki Izumi, Takashi Noda
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 299-303
Technical Note | doi.org/10.13182/NSE70-A20718
Interface Conditions for Discontinuous Flux Synthesis Methods
William B. Terney
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 303-307
Technical Note | doi.org/10.13182/NSE70-A20719
A Slow Neutron Scattering Routine from the Gas Model
John R. Eriksson
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 307-309
Technical Note | doi.org/10.13182/NSE70-A20720
Geometric Interpretation of the Function g(c,µ) of Neutron Transport Theory
Perry A. Newman, Robert L. Bowden
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 309-310
Technical Note | doi.org/10.13182/NSE70-A20721
Comparisons of Monte Carlo Calculations to Measurements of Neutron Leakage from the TSF-SNAP Reactor
V. R. Cain
Nuclear Science and Engineering | Volume 41 | Number 2 | August 1970 | Pages 310-315
Technical Note | doi.org/10.13182/NSE70-A20722
Heat Transfer to Mercury Flowing In-Line Through an Unbaffled Rod Bundle: Effect of Rod Displacement on Local Surface Temperature and Local Heat Flux
O. E. Dwyer, P. J. Hlavac, M. A. Helfant
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 321-335
Technical Paper | doi.org/10.13182/NSE70-A19090
The Two-Phase Critical Discharge of Initially Saturated or Subcooled Liquid
Robert E. Henry
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 336-342
Technical Paper | doi.org/10.13182/NSE70-A19091
Statistical Evaluation of the Maximum Temperatures in Reactor Cores
A. Amendola
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 343-350
Technical Paper | doi.org/10.13182/NSE70-A19092
The Total Neutron Cross Section of Lithium-7 and Carbon from 100 to 1500 keV
J. W. Meadows, J. F. Whalen
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 351-356
Technical Paper | doi.org/10.13182/NSE70-A19093
Measurements of Thermal Neutron Spectra in Heterogeneous Lattices by Foil Activation
G. W. Dixon, R. Sher
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 357-366
Technical Paper | doi.org/10.13182/NSE70-A19094
Comparison of Calculated and Measured Energy-Dependent Activation Rates for NERVA-Type Reactor
S. Salah, W. D. Rankin, V. S. Oblock
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 367-380
Technical Paper | doi.org/10.13182/NSE70-A19095
Continuous Slowing Down Theory Applied to Fast-Reactor Assemblies
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 381-393
Technical Paper | doi.org/10.13182/NSE70-A19096
An Exact Solution of The Neutron Slowing Down Equation
D. Stefanović
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 394-398
Technical Paper | doi.org/10.13182/NSE70-A19097
Higher Order Variational Principles and Iterative Processes
J. Devooght
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 399-403
Technical Paper | doi.org/10.13182/NSE70-A19098
Time-Dependent Neutron Transport Theory for Fast Pulsed Assemblies
H. N. Knickle, P. B. Daitch
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 404-416
Technical Paper | doi.org/10.13182/NSE70-A19099
The Information in Neutron Fluctuations
Robert W. Albrecht, Walter Seifritz
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 417-430
Technical Paper | doi.org/10.13182/NSE70-A19100
Alternating Direction Methods for the Reactor Kinetics Equations
Wm. H. Reed, K. F. Hansen
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 431-442
Technical Paper | doi.org/10.13182/NSE41-431
Characterization of Porous Media in Terms of Their Gas Transmission Properties
E. Creutz
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 443-445
Technical Note | doi.org/10.13182/NSE70-A19102
A Measurement of the Radiation Width of the 2.85 keV Neutron Resonance and of the Thermal Neutron Capture Cross Section in Sodium
N. Yamamuro, R. W. Hockenbury, R. C. Block, R. H. Wolfe
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 445-449
Technical Note | doi.org/10.13182/NSE70-A19103
Calculated Activation of Copper and Iron by 3-GeV Protons
T. W. Armstrong, J. Barish
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 449-451
Technical Note | doi.org/10.13182/NSE70-A19104
Effects of Plutonium-239 Alpha Uncertainties on some Significant Integral Quantities of Fast Reactors
A. Gandini, M. Salvatores
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 452-455
Technical Note | doi.org/10.13182/NSE70-A19105
Resolved Narrow Resonance Reaction Rates in Fast-Reactor Mixtures
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 455-457
Technical Note | doi.org/10.13182/NSE70-A19106
Continuous Slowing Down Theory for Anisotropic Elastic Neutron Moderation in the PN and BN Representations
Nuclear Science and Engineering | Volume 41 | Number 3 | September 1970 | Pages 457-461
Technical Note | doi.org/10.13182/NSE70-A19107
