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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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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.
Jump to:
Heat Transfer to Liquid Metals Flowing Turbulently in Eccentric Annuli—II
W. S. Yu, O. E. Dwyer
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE67-A18036
Material Bucklings for 1.002, 1.25, and 1.95 wt% Uranium-235-Enriched Uranium Tubes in Light Water
C. L. Brown, R. C. Lloyd
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 10-15
Technical Paper | doi.org/10.13182/NSE67-A18037
Fast Neutron Spectroscopy by Proton-Recoil Proportional Counting
E. F. Bennett
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 16-27
Technical Paper | doi.org/10.13182/NSE67-A18038
Neutron Spectrum Measurement in a Fast Critical Assembly
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 28-33
Technical Paper | doi.org/10.13182/NSE67-A18039
Direct Determination of Uranium-235 Capture-to-Fission Ratio in a Zero-Power Reactor
W. C. Redman, M. M. Bretscher
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 34-44
Technical Paper | doi.org/10.13182/NSE67-A18040
Slowing Down of Neutrons in Zirconium Hydride
Pekka Jauho, Jussi Manninen
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 45-50
Technical Paper | doi.org/10.13182/NSE67-A18041
Slowing Down Spectra of Neutrons in Lithium Hydride
V. V. Verbinski
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 51-66
Technical Paper | doi.org/10.13182/NSE67-A18042
Angular Distributions of Low-Energy Neutrons Leaking from Various Scattering Materials
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 67-79
Technical Paper | doi.org/10.13182/NSE67-A18043
Experimental Investigation of Fast Neutron Decays in Lead Assemblies
L. E. Beghain, F. Hofmann, S. Wilensky
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 80-84
Technical Paper | doi.org/10.13182/NSE67-A18044
The Determination of the Fast-Fission Cross Section of Protactinium-233 with Fission Neutrons
H. R. von Gunten, R. F. Buchanan, A. Wyttenbach, K. Behringer
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 85-94
Technical Paper | doi.org/10.13182/NSE67-A18045
Monte Carlo Calculations of Resonance Integral of 232Th
Bal Raj Sehgal
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 95-103
Technical Paper | doi.org/10.13182/NSE67-A18046
Milne Problem for Thermal Neutrons with Absorption
Jacek Arkuszewski
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 104-119
Technical Paper | doi.org/10.13182/NSE67-A18047
Stability Extrema in Nuclear Power Systems with Design Uncertainties
T. W. Kerlin
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 120-130
Technical Paper | doi.org/10.13182/NSE67-A18048
Selective Ion-Exchange Sorption of Cesium-137 and Iodine-131 from Borated Solutions
B. N. Dickinson
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 131-132
Technical Note | doi.org/10.13182/NSE67-A18049
An Improved Treatment of Scattering Resonances in Slab Geometry
Sanford C. Cohen
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 133-135
Technical Note | doi.org/10.13182/NSE67-A18050
Influence of Molecular Binding Effects in Water on Measured Resonance Integrals
J. Hardy, Jr.
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 135-136
Technical Note | doi.org/10.13182/NSE67-A18051
An Analytic Treatment of the “Flux Bump” in Resonance Absorption
G. C. Pomraning, M. W. Dyos
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 137-139
Technical Note | doi.org/10.13182/NSE67-A18052
Calculations of the Radiation Hazard Due to Exposure of Supersonic Aircraft to Solar-Flare Protons
M. Leimdorfer, R. G. Alsmiller, Jr., and R. T. Boughner
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 151-157
Technical Paper | doi.org/10.13182/NSE67-A18259
High-Energy Nucleon Transport and Space Vehicle Shielding
R. G. Alsmiller, Jr.
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 158-189
Technical Paper | doi.org/10.13182/NSE67-A18260
Electron Transport Theory, Calculations, and Experiments
C. D. Zerby and F. L. Keller
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 190-218
Technical Paper | doi.org/10.13182/NSE67-A18261
Adjoint and Importance in Monte Carlo Application
R. R. Coveyou, V. R. Cain, and K. J. Yost
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 219-234
Technical Paper | doi.org/10.13182/NSE67-A18262
Variance of Certain Flux Estimators Used in Monte Carlo Calculations
Francis H. Clark
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 235-239
Technical Paper | doi.org/10.13182/NSE67-1
A Study of the Angular and Energy Distributions of Radiation at Small Distances from a Point Source of Gamma Rays or Neutrons
Charles Eisenhauer
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 240-251
Technical Paper | doi.org/10.13182/NSE67-A18264
Doses Behind Vertical and Horizontal Barriers from a Plane Source of 1.25 MeV Gamma-Ray Photon
Dominic J. Raso and Stanley Woolf
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 252-264
Technical Paper | doi.org/10.13182/NSE67-A18265
Deep Penetration of Radiation by the Method of Invariant Imbedding
D. R. Mathews, K. F. Hansen, and E. A. Mason
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 263-270
Technical Paper | doi.org/10.13182/NSE67-A18266
One-Velocity Neutron Transport Problems by the Transfer Matrix Method
Raphael Aronson
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 271-282
Technical Paper | doi.org/10.13182/NSE67-A18267
Measurements and Calculations of the Spectral and Spatial Details of the Fast-Neutron Flux in Water Shields
V. V. Verbinski, M. S. Bokhari, J. C. Courtney, and G. E. Whitesidestt
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 283-298
Technical Paper | doi.org/10.13182/NSE67-A18268
Measurements of the Spectra of Uncollided Fission Neutrons Transmitted Through Thick Samples of Nitrogen, Oxygen, Carbon, and Lead: Investigation of the Minima in Total Cross Sections
C. E. Clifford, E. A. Straker, F. J. Muckenthaler, V. V. Verbinski, R. M. Freestone, Jr., K. M. Henry, and W. R. Burrus
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 299-307
Technical Paper | doi.org/10.13182/NSE67-A18269
Neutron-Attenuation Experiments in Iron-Water Configurations
B. Chinaglia and D. Monti, C. Fedrighini and A. M. Moncassoli
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 308-317
Technical Paper | doi.org/10.13182/NSE67-A18270
Experimental Differential Number, Energy and Exposure Albedos for Sem-finite Media, for Normally Incident Gamma Photons
J. J. Steyn, D. G. Andrews
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 318-327
Technical Paper | doi.org/10.13182/NSE67-A18271
Capture and Fission Gamma-Ray Effective Spectra for Shielding
Donald J. Dudziak
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 328-337
Technical Paper | doi.org/10.13182/NSE67-A18272
High-Energy Accelerator Shield-Leakage Neutron Spectra
Keran O'Brien, Robert Sanna, Mary Alberg, James E. McLaughlin, and Sam A. Rothenberg
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 338-347
Technical Paper | doi.org/10.13182/NSE67-A18273
Neutron Exposure of the PM-2A Reactor Vessel
K. Shure and Carl T. Oberg
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 348-359
Technical Paper | doi.org/10.13182/NSE67-A18274
An Analysis of a Shielding Experiment Performed in a Real Fallout Field
R. L. French, J. H. Price, and K. W. Tompkins
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 360-366
Technical Paper | doi.org/10.13182/NSE67-A18275
Neutron Air-Transport Data for the Design of Protective Structures
R. H. Karcher
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 367-387
Technical Paper | doi.org/10.13182/NSE67-A18276
Investigation of the Floor-Barrier Reduction Factor Used In Structure Shielding Theory
A. L. Kaplan
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 388-393
Technical Paper | doi.org/10.13182/NSE67-A18277
Gamma-Ray Scattering Near an Air-Ground Interface
E. T. Clarke
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 394-402
Technical Paper | doi.org/10.13182/NSE67-A18278
The Close-in Exposure Field From Point Isotropic Gamma-Ray Source Located at an Air-Ground Interface
A. B. Chilton
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 403-410
Technical Paper | doi.org/10.13182/NSE67-A18279
Calculation of Doubly Differential Current Albedos for Epicadmium Neutrons Incident on Concrete and Comparison of the Reflected Subcadmium Component with Experiment
W. A. Coleman, R. E. Maerker, F. J. Muckenthaler, and P. N. Stevens
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 411-422
Technical Paper | doi.org/10.13182/NSE67-A18280
Monte Carlo Calculations, Using the Albedo Concept, of the Fast-Neutron Dose Rates along the Center Lines of One- and Two-Legged Square Concrete Open Ducts and Comparison with Experiment
R. E. Maerker and F. J. Muckenthaler
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 423-433
Technical Paper | doi.org/10.13182/NSE67-A18281
On the Attenuation of Neutrons and Photons Duct Filled with a Helical Steel Plug
E. Aalto and Å. Krell
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 433-440
Technical Paper | doi.org/10.13182/NSE67-A18282
Albedo Component of Gamma Rays Passing Through a Cylindrical Duct
Y. Higashihara, Masaru Nakai, Masanori Okubo,
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 441-449
Technical Paper | doi.org/10.13182/NSE67-A18283
Gamma-Ray Streaming Through a Straight Cylindrical Duct
Mitsuo Shindo, Akira Tsuruo, Shun-ichi Miyasaka, Mitsuyuki Kitazume, Jun-ichi Miyakoshi
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 450-463
Technical Paper | doi.org/10.13182/NSE67-A18284
Weight Optimization of Gamma-Ray Shields Using Layered Media and Spherical Geometry
Alfred F. Rohach
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 464-466
Technical Note | doi.org/10.13182/NSE67-A18285
Empirical Formulas for Secondary-Nucleon-Production Cross Sections
W. R. Yucker
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Page 467
Technical Note | doi.org/10.13182/NSE67-A18286
Few-Group and Multigroup Calculations of Neutron Penetration
K. Shure
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 468-471
Technical Note | doi.org/10.13182/NSE67-A18287
Heating in Infinite Cylinders by Uniform Gamma-Ray Sources
C. W. Nestor, Jr., and H. C. Claiborne
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 472-474
Technical Note | doi.org/10.13182/NSE67-A18288
A Markov Matrix Treatment of Neutron Diffusion in Thin Slabs
M. L. Eaton and C. M. Huddleston
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 475-477
Technical Note | doi.org/10.13182/NSE67-A18289
Differential Neutron Albedo For Finite Slabs
Duane R. Doty
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 478-480
Technical Note | doi.org/10.13182/NSE67-A18290
A Modified Formula for Differential Exposure Albedo for Gamma Rays Reflected from Concrete
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 481-482
Technical Note | doi.org/10.13182/NSE67-A18291
Air-Ground Interface Effects on the Exposure from Elevated 137Cs y Sources
C. E. Clifford and G. D. Wait
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 483-484
Technical Note | doi.org/10.13182/NSE67-A18292
The Small-Angle Limit for Twice-Scattered Gamma Rays from a Point-lsotropic Source
Edgar E. Morris and L. V. Spencer
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 485-487
Technical Note | doi.org/10.13182/NSE67-A18293
Few-Group Approximations Based on a Variational Principle
A. F. Henry
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 493-510
Technical Paper | doi.org/10.13182/NSE86-A17615
The Thermal-Neutron Milne Problem with a Two-Term Degenerate Kernel
M. M. R. Williams
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 511-519
Technical Paper | doi.org/10.13182/NSE86-A17616
Scattering Functions for Low-Energy Neutron Collisions in a Maxwellian Monatomic Gas
G. Lansing Blackshaw, Raymond L. Murray
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 520-532
Technical Paper | doi.org/10.13182/NSE86-A17617
Neutron-Flux Spectral Determination by Foil Activation
W. N. McElroy, S. Berg, G. Gigas
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 533-541
Technical Paper | doi.org/10.13182/NSE86-A17618
Continuity Conditions for a Homogeneous or Heterogeneous PN Approximation
James A. Davis
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 542-548
Technical Paper | doi.org/10.13182/NSE86-A17619
Effects of the Flat-Flux and Infinite-Mass Approximation on Resonance Absorption
Hans Ludewig
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 549-556
Technical Paper | doi.org/10.13182/NSE86-A17620
Multiplication Factor of Uranium Metal by One-Velocity Monte Carlo Calculations
John T. Mihalczo
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 557-563
Technical Paper | doi.org/10.13182/NSE86-A17621
The Effect of Air Channels on the Diffusion Length of Thermal Neutrons in Light Water
Y. Segal, S. Zamir
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 564-567
Technical Paper | doi.org/10.13182/NSE86-A17622
Fission-Neutron Age Measurements in Aluminum-Water Mixtures
J. D. Spencer, T. G. Williamson
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 568-572
Technical Paper | doi.org/10.13182/NSE86-A17623
Experimental Application of the Time-Optimal Xenon Shutdown Program
John J. Roberts, R. F. Fleming, Harold P. Smith, Jr.
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 573-580
Technical Paper | doi.org/10.13182/NSE86-A17624
The Influence of Source Geometry on Fission-Fragment Escape Properties
E. E. Lewis, R. Pfeffer
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 581-585
Technical Paper | doi.org/10.13182/NSE86-A17625
Bremsstrahlung from 90Sr-90Y in Thin Absorbers
Thomas S. Bustard, Joseph Silverman
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 586-596
Technical Paper | doi.org/10.13182/NSE86-A17626
A Method of Calculating Asymptotic and Transient Material Bucklings of a Uniform Rod Lattice
J. D. Stewart
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 597-598
Technical Note | doi.org/10.13182/NSE86-A17627
The Boundary Conditions at the Interface between a Lattice Core and a Homogeneous Reflector
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 598-600
Technical Note | doi.org/10.13182/NSE86-A17628
Controllability of the Spatial Flux Shape
Donald M. Wiberg
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 600-604
Technical Note | doi.org/10.13182/NSE86-A17629
