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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
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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.
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Use of Hydraulic Models in Nuclear Reactor Design
G. Hetsroni
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE67-A18661
A Visual and Frictional Pressure-Drop Study of Natural-Circulation Single-Component Two-Phase Flow at Low Pressures
Min-Nan Huang, M. M. El-Wakil
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 12-19
Technical Paper | doi.org/10.13182/NSE67-A18662
The Use of Spherical UO2 in a Cermet Fuel Plate
F. C. Robertshaw, R. K. Betts, D. E. Conner
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 20-33
Technical Paper | doi.org/10.13182/NSE67-A18663
Performance of Pyrolytic Carbon-Coated Uranium Oxide Particles During Irradiation at High Temperature
P. E. Reagan, R. L. Beatty, E. L. Long, Jr.
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 34-41
Technical Paper | doi.org/10.13182/NSE67-A18664
Irradiation Behavior of Uranium Fuel Tubes in a Pressurized Heavy-Water Reactor
C. L. Angerman, W. R. McDonell
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 42-50
Technical Paper | doi.org/10.13182/NSE67-A18665
The Compatibility of Graphite with Cesium
F. J. Salzano, S. Aronson
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 51-54
Technical Paper | doi.org/10.13182/NSE67-A18666
Beta Particle Backscattering
Thomas S. Bustard, Joseph Silverman
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 55-61
Technical Paper | doi.org/10.13182/NSE67-A18667
Measurement of Fissions Produced in Bulk Plutonium-239 by 2-eV to 10-keV Neutrons
J. B. Czirr, R. L. Bramblett
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 62-71
Technical Paper | doi.org/10.13182/NSE67-A18668
Power Oscillations and the Describing Function in Reactors with Linear Feedback
A. Ziya Akcasu, Louis M. Shotkin
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 72-81
Technical Paper | doi.org/10.13182/NSE67-A18669
The Application of a Hybrid Computer to the Analysis of Transient Phenomena in a Fast Reactor Core
C. K. Sanathanan, J. C. Carter, L. T. Bryant, L. W. Amiot
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 82-92
Technical Paper | doi.org/10.13182/NSE67-A18670
Solution of Group-Diffusion Equation Using Green's Function
Keisuke Kobayashi, Hiroshi Nishihara
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 93-104
Technical Paper | doi.org/10.13182/NSE67-A18671
An Analogy Between Time-Dependent Diffusion Theory and Classical Mechanics
B. E. Clancy, M. Tavel
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 105-110
Technical Paper | doi.org/10.13182/NSE67-A18672
Inelastic Scattering Measurements in a Fast Reactor by the Spherical Shell Method
William G. Davey, Paul I. Amundson
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 111-123
Technical Paper | doi.org/10.13182/NSE67-A18673
Anisotropic Scattering Coefficients in the Constant Cross-Section Transport Equation
Raymond L. Murray, Charles E. Siewert, Walter J. Harrington
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 124-126
Technical Paper | doi.org/10.13182/NSE67-A18674
The Effect of Anisotripic Scattering in Plane-Geometry Transport Theory and Monte Carlo Calculations
M. R. Mendelson
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 127-132
Technical Paper | doi.org/10.13182/NSE67-A18675
Total Neutron Cross Section of Protactinium-233
F. B. Simpson, J. W. Codding, Jr.
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 133-138
Technical Paper | doi.org/10.13182/NSE67-A18676
The Thermal-Neutron Capture Cross Section of 147Sm
L. Forman, F. A. White
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 139-143
Technical Paper | doi.org/10.13182/NSE67-A18677
Dose Buildup Factors of Plane Parallel Barriers For 137Cs Plane Monodirectional Source
Kozo Tamura, Akira Tsuruo
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 144-145
Technical Note | doi.org/10.13182/NSE67-A18678
Method for Calculating Average Thermal Neutron Parameters
J. J. Bulmer, P. B. Daitch
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 145-148
Technical Note | doi.org/10.13182/NSE67-A18679
Comment on the Calculation of the Scattering Cross Section for Multiple Resonances
John M. Otter
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 149-150
Technical Note | doi.org/10.13182/NSE67-A18680
A Limitation of the Roussopoulos Variational Principle?
G. C. Pomraning
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 150-152
Technical Note | doi.org/10.13182/NSE67-A18681
Asymptotic Neutron Pulse Velocity and the System Dispersion Law
M. N. Moore
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 152-154
Technical Note | doi.org/10.13182/NSE67-A18682
The Application of Lie Series to Reactor Theory
J. Mettnig, T. Auerbach
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 159-165
Technical Paper | doi.org/10.13182/NSE67-A17465
Canonical and Involutory Transformations of the Variational Problems of Transport Theory
S. Kaplan, James A. Davis
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 166-176
Technical Paper | doi.org/10.13182/NSE67-A17466
Applications of the Invariant Imbedding Method to Monoenergetic Neutron Transport Theory in Slab Geometry
John O. Mingle
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 177-189
Technical Paper | doi.org/10.13182/NSE67-A17467
A Two-Region Problem in Time-Dependent Monoenergetic Neutron Transport Theory. I. Analysis
R. C. Erdmann, H. Lurie
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 190-197
Technical Paper | doi.org/10.13182/NSE67-A17468
A Two-Region Problem in Time-Dependent Monoenergetic Neutron Transport Theory. II. Applications
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 198-202
Technical Paper | doi.org/10.13182/NSE67-A17469
Solution of the Neutron Slowing Down Problem via a Multiple Collision Approach
Constantin Syros
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 203-214
Technical Paper | doi.org/10.13182/NSE67-A17470
First-Flight Collision Probabilities in Pin Clusters and Rod Lattices
L. Amyot, P. Benoist
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 215-225
Technical Paper | doi.org/10.13182/NSE67-A17471
Determination of Stability Domains in Point Reactor Dynamics
J. Devooght, H. B. Smets
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 226-236
Technical Paper | doi.org/10.13182/NSE67-A17472
Point-Reactor Theory of Rossi-Alpha Experiment
Dušan Babala
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 237-242
Technical Paper | doi.org/10.13182/NSE67-A17473
Interval Distributions in Neutron Counting Statistics
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 243-246
Technical Paper | doi.org/10.13182/NSE67-A17474
An Analysis of Neutron Thermalization in Beryllium
R. R. Lee, P. B. Daitch
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 247-258
Technical Paper | doi.org/10.13182/NSE67-A17475
Neutron Thermalization in Light Water
J. C. Young, G. D. Trimble, J. M. Neill, G. K. Houghton, D. H. Houston, J. R. Beyster
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 259-269
Technical Paper | doi.org/10.13182/NSE67-A17476
Analysis of Critical Experiments with Organic-Moderated Assemblies
G. Bitelli, R. Martinelli, F. V. Orestano, E. Santandrea
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 270-276
Technical Paper | doi.org/10.13182/NSE67-A17477
A Method for Absolute Determination of 238U Capture Rates in Fast Zero-Power Reactors
H. Seufert, D. Stegemann
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 277-285
Technical Paper | doi.org/10.13182/NSE67-A17478
The Thermal-Neutron Capture Cross Section of Deuterium
Janet S. Merritt, J. G. V. Taylor, A. W. Boyd
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 286-292
Technical Paper | doi.org/10.13182/NSE67-A17479
Total Cross Sections of Calcium and Potassium for Fast Neutrons
E. G. Bacon, Jr., C. J. Wickstrom
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 293-295
Technical Paper | doi.org/10.13182/NSE67-A17480
Effective Hot-Channel Factors for “Flat” Power Reactors
F. D. Judge, L. S. Bohl
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 296-300
Technical Paper | doi.org/10.13182/NSE67-A17481
Liquid-Metal Heat Transfer in a Parallel-Plate Channel with Periodic Boundary Conditions
Chia-Jung Hsu
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 301-305
Technical Note | doi.org/10.13182/NSE67-A17482
The Gamma-Ray Branching of Krypton-85
B. Denecke, E. De Roost, A. Spernol, R. Vaninbroukx
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 305-306
Technical Note | doi.org/10.13182/NSE67-A17483
Some Measurements of Decay Constants Close to (v ∑inel)min in Pulsed BeO Assemblies
A. I. M. Ritchie, M. T. Rainbow
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 306-308
Technical Note | doi.org/10.13182/NSE67-A17484
Computation of Time-Dependent Neutron Spectra in D2O
G. P. Calame
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 308-310
Technical Note | doi.org/10.13182/NSE67-A17485
On the Boundary Condition on the Flux of Monoenergetic Neutrons at a Plane Black Boundary
J. D. Stewart
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Page 310
Technical Note | doi.org/10.13182/NSE67-A17486
An Extension of the Path-Length Formalism to Anisotropic Charged-Particle Sources
E. E. Lewis
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 311-312
Technical Note | doi.org/10.13182/NSE67-A17487
Stability Considerations in Two-Phase Flow
Louis M. Shotkin
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 317-324
Technical Paper | doi.org/10.13182/NSE67-A28945
The Chemistry of Hydrogen in Liquid-Alkali-Metal Mixtures Useful as Nuclear Reactor Coolants - I. Sodium-Potassium Eutectic
Edgar L. Compere and Jouko E. Savolainen
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 325-337
Technical Paper | doi.org/10.13182/NSE67-A28946
Recovery of Beryllium from Acid Leaches of Beryl by Solvent Extraction
Joseph P. Surls, Jr. and Robert R. Grinstead
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 338-345
Technical Paper | doi.org/10.13182/NSE67-A28947
Preparation of High-Purity Beryllium Compounds by Solvent Extraction
Robert R. Grinstead and Joseph P. Surls, Jr.
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 346-352
Technical Paper | doi.org/10.13182/NSE67-A28948
The Absorbed Dose Rate from Both the Uncollided and Once-Collided Flux of Gamma Rays at the Center of a Spherical Shell Shield Bombarded by an Isotropic Flux Spectrum of Protons
Richard Madey and Harold Shulman
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 353-358
Technical Paper | doi.org/10.13182/NSE67-A28949
Parameters for the First Neutron Resonance in 113Cd
R. Ö. Akyüz, Ç. Cansoy, and F. Domaniç
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 359-363
Technical Paper | doi.org/10.13182/NSE67-A28950
Angle-Space Synthesis-an Approach to Transport Approximations
S. Kaplan, J. A. Davis, and M. Natelson
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 364-375
Technical Paper | doi.org/10.13182/NSE67-A28951
Multitable Treatments of Anisotropic Scattering in SN Multigroup Transport Calculations
G. I. Bell, G. E. Hansen, and H. A. Sandmeier
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 376-383
Technical Paper | doi.org/10.13182/NSE67-2
Noise-Equivalent Source in Nuclear Reactors
Keiichi Saito
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 384-396
Technical Paper | doi.org/10.13182/NSE67-A28953
Study of the Kinetics of Thermalized Neutron Populations in Multiplying or Nonmultiplying Heterogeneous Media
V. Deniz
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 397-403
Technical Paper | doi.org/10.13182/NSE67-A28954
On the Experimental Application of the Neutron-Wave Technique to Thermal-Neutron Systems
R. S. Booth, R. H. Hartley, R. B. Perez
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 404-414
Technical Paper | doi.org/10.13182/NSE67-A28955
An Approximate Theory for the Slowing Down of Neutrons in a Nonmultiplying Medium
H. G. Kaper
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 415-425
Technical Paper | doi.org/10.13182/NSE67-A28956
Synthesis of Three-Dimensional Flux Shapes Using Discontinuous Sets of Trial Functions
J. B. Yasinsky and S. Kaplan
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 426-437
Technical Paper | doi.org/10.13182/NSE67-A28957
A General Modal-Expansion Method for Obtaining Approximate Equations for Linear Systems
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 438-442
Technical Paper | doi.org/10.13182/NSE67-A28958
Fast-Reactor Calculational Models
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 443-449
Technical Paper | doi.org/10.13182/NSE67-A28959
The Influence of Chemical Binding on Milne Problem Neutron Leakage Spectra
J. M. Kallfelz and K. H. Beckurts
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 450-452
Technical Note | doi.org/10.13182/NSE67-A28960
On the Noise-Equivalent Source in Zero-Power Reactor
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 452-456
Technical Note | doi.org/10.13182/NSE67-A28961
Properties of the Relaxation Lengths in PL, Double-PL, and Angle-Space Synthesis-Type Approximations
S. Kaplan
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 456-458
Technical Note | doi.org/10.13182/NSE67-A28962
The Correlation of the Energy of Single-Neutron Resonances Determined by Time-of-Flight Methods
S. A. R. Wynchank and W. W. Havens, Jr.
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 458-461
Technical Note | doi.org/10.13182/NSE67-A28963
Note on the Half-Width of the Neutron Pulse of a Pulsed Reactor
G. Kistner
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Page 461
Technical Note | doi.org/10.13182/NSE67-A28964
Extrapolation Distance in Water for Small Geometry
V. A. Swanson and J. A. DeJuren
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 461-462
Technical Note | doi.org/10.13182/NSE67-A28965
A Summation Scheme for Certain Series in Neutron Thermalization
A. A. Virjo
Nuclear Science and Engineering | Volume 28 | Number 3 | June 1967 | Pages 462-463
Technical Note | doi.org/10.13182/NSE67-A28966
