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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
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IEA report: Challenges need to be resolved to support global nuclear energy growth
The International Energy Agency published a new report this month outlining how continued innovation, government support, and new business models can unleash nuclear power expansion worldwide.
The Path to a New Era for Nuclear Energy report “reviews the status of nuclear energy around the world and explores risks related to policies, construction, and financing.”
Find the full report at IEA.org.
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A Theory for Predicting Pressure Gradients for Two-Phase Critical Flow
Hans K. Fauske
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE63-A17204
Orthogonal Polynomial Angular Expansion of the Boltzmann Equation
G. C. Pomraning, M. Clark, Jr.
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 8-17
Technical Paper | doi.org/10.13182/NSE63-A17205
Simulated Boiling Water Reactor and Superheat Reactor Corrosion Facility
M. D. Fitzsimmons, W. L. Pearl, M. Siegler
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 18-29
Technical Paper | doi.org/10.13182/NSE63-A17206
Fuel Cladding Corrosion Testing in Simulated Superheat Reactor Environment Phase I. General Corrosion Type 304 Stainless Steel
G. G. Gaul, W. L. Pearl
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 30-41
Technical Paper | doi.org/10.13182/NSE63-A17207
Resonance Absorption and the Resonance Disadvantage Factor
S. Iijima
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 42-46
Technical Paper | doi.org/10.13182/NSE63-A17208
Initial Conversion Ratios and Fast Fission Factors in Heavy-Water Natural-Uranium Lattices Using 19-Element UO2 Fuel Rods
B. G. Chidley, T. J. Manuel, P. R. Tunnicliffe
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 47-54
Technical Paper | doi.org/10.13182/NSE63-A17209
Transport Solutions to the One-Dimensional Critical Problem
George J. Mitsis
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 55-64
Technical Paper | doi.org/10.13182/NSE63-A17210
Synthetic Method Solution of the Transport Equation
H. J. Kopp
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 65-74
Technical Paper | doi.org/10.13182/NSE63-1
Research Facility for the Synthesis and Fabrication of Refractory Plutonium Materials
F. A. Saulino, J. C. Andersen, K. M. Taylor
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 75-81
Technical Paper | doi.org/10.13182/NSE63-A17212
The Investigation of Nonelastic Cross Sections for Iron by the Nanosecond Pulsed Neutron Source Technique
L. E. Beghian, A. E. Profio, J. Weber, S. Wilensky
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 82-90
Technical Paper | doi.org/10.13182/NSE63-A17213
Propagation of Neutron Waves in Moderating Media
R. B. Perez, R. E. Uhrig
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 90-100
Technical Paper | doi.org/10.13182/NSE63-A17214
A General Method for Evaluating the Effects of Uncertainties in Design Variables on Core Thermal Performance
A. C. Nelson, JR., W. S. Minkler
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 101-110
Technical Paper | doi.org/10.13182/NSE63-A17215
Symmetry Properties of Some Eigenfunctions Occurring in Reactor Analysis
Mark Goldsmith
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 111-124
Technical Paper | doi.org/10.13182/NSE17-111-124
Gamma-Ray Scattering by Concrete Surfaces
Eric T. Clarke, John F. Batter
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 125-130
Technical Paper | doi.org/10.13182/NSE63-A17217
Neutron Rethermalization in Graphite and Water
R. A. Bennett
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 131-143
Technical Paper | doi.org/10.13182/NSE63-A17218
Effective Resonance Integral for Pu240 in Plutonium-Aluminum Alloy Rods
P. F. Nichols
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 144-148
Technical Paper | doi.org/10.13182/NSE63-A17219
Mechanical Dejacketing of Liquid-Metal-Bonded Nuclear Fuels: An Evaluation of a Hydraulic Method and Two Alternative Methods with Spent Fuel from Core 1 of the Sodium Reactor Experiment
C. D. Watson, G. A. West, W. F. Schaffer, JR.
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 149-164
Technical Paper | doi.org/10.13182/NSE63-A17220
An Elastic-Plastic Cylinder with Free Ends and Internal Heat Generation
William A. Beyer
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 179-184
Technical Paper | doi.org/10.13182/NSE63-A28876
Diffusion Parameters for Thermal Neutrons
R. Kladnik.
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 185-191
Technical Paper | doi.org/10.13182/NSE63-A28877
Properties of Irradiated and Periodically Annealed Graphite
S. Aronson, D. G. Schweitzer, R. M. Singer
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 192-193
Technical Paper | doi.org/10.13182/NSE63-A28878
A Measurement of the Doppler Effect in Thorium in a Fast Neutron Energy Spectrum with a Median Fission Energy of 190 kev
T. H. SPRINGER AND S. G. CARPENTER.
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 194-199
Technical Paper | doi.org/10.13182/NSE63-A28879
Physical Properties of Molten Reactor Fuels and Coolants
W. D. Powers, S. I. Cohen, N. D. Greene
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 200-211
Technical Paper | doi.org/10.13182/NSE63-5
Asymptotic and Transient Analysis of Pulsed Moderators
P. B. Daitch, D. B. Ebeoglu
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 212-219
Technical Paper | doi.org/10.13182/NSE63-A28881
On the Asymptotic Form of the Collision Density
C. A. Wilkins
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 220-222
Technical Paper | doi.org/10.13182/NSE63-A28882
The Diffusion Parameters of Heavy Water
N. K . Ganguly, F. C. Cobb, A. W. Waltner
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 223-226
Technical Paper | doi.org/10.13182/NSE63-A28883
A New Asymptotic Diffusion Theory
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 227-233
Technical Paper | doi.org/10.13182/NSE63-A28884
Fission Product Recovery from Waste Solutions by Solvent Extraction
D. E. Horner, D. J. Grouse, K. B. Brown, B. Weaver
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 234-246
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28885
Types of Acidic Organophosphorus Extractants and Their Applications to Transuranic Separations
G. W. Mason, D. F. Peppard
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 247-251
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28886
Application of Amine and Phosphonate Extractants to Transplutonium Element Production
R. E. Leuze, R. D. Baybarz, Boyd Weaver
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 252-258
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28887
Solvent Extraction, Recovery, and Purification of Beryllium from Ores
R. A. Wells, D. A. Everest, A. A. North
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 259-267
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28888
Purification of Beryllium by Acetylacetone-EDTA Solvent Extraction
R. E. Moore, J. H. Shaffer, C. F. Baes, Jr., H. F. McDuffie, C. E. L. Bamberger
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 268-273
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28889
Amines as Extractants
C. F. Coleman
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 274-286
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28890
Amines as Extractants—Studies of the Organic Phase
W. E. Keder, A. S. Wilson
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 287-297
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28891
The Eurex Process: Processing of Irradiated U-Al Alloys by Amine Solvent Extraction
Nuclear Science and Engineering | Volume 17 | Number 2 | October 1963 | Pages 298-308
Solvent Extraction Chemistry Symposium. Part II. | doi.org/10.13182/NSE63-A28892
Parameters of the 132 ev Neutron Resonance in Co53
A. P. Jain, R. E. Chrien, J. A. Moore, H. Palevsky
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 319-324
Technical Paper | doi.org/10.13182/NSE63-A17377
Total Neutron Cross Sections of Na, K, and Ca from 0.9 Mev to 2.1 Mev
F. J. Vaughn, W. L. Imhof, R. G. Johnson
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 325-328
Technical Paper | doi.org/10.13182/NSE63-A17378
Thermal Activation Cross Sections and Resonance Integrals of In115
K. H. Beckurts, M. Brose, M. Knoche, G. Kruger, W. PÖNitz, H. Schmidt
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 329-335
Technical Paper | doi.org/10.13182/NSE63-A17379
On the Transfer of Heat to Fluids Flowing through Pipes, Annuli, and Parallel Plates
O. E. Dwyer
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 336-344
Technical Paper | doi.org/10.13182/NSE63-A17380
The Backscattering of Gamma Radiation from Plane Concrete Walls
Martin LeimdÖRfer
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 345-351
Technical Paper | doi.org/10.13182/NSE63-A17381
The Backscattering of Gamma Radiation from Spherical Concrete Walls
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 352-356
Technical Paper | doi.org/10.13182/NSE63-A17382
Multiple Reflection of Gamma Radiation in a Spherical Concrete Wall Room
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 357-364
Technical Paper | doi.org/10.13182/NSE63-A17383
Techniques for the Fabrication of Ultra-thin Metallic Foils
Frank J. Karasek
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 365-370
Technical Paper | doi.org/10.13182/NSE63-A17384
Neutron Cross Section Measurements on Fission Product Samarium and Iodine
N. J. Pattenden
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 371-380
Technical Paper | doi.org/10.13182/NSE63-A17385
Uranium Dioxide-Cladding Interactions. Axial Expansion of UO2 Column in Fuel Elements
C. N. Spalaris
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 381-391
Technical Paper | doi.org/10.13182/NSE63-A17386
Some Aspects of Neutron Slowing-Down Distributions in Hydrogeneous Media
J. J. Mcinerney
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 392-397
Technical Paper | doi.org/10.13182/NSE63-A17387
Neutron-Spectra Calculations for Radiation-Damage Studies
R. E. Dahl, H. H. Yoshikawa
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 398-403
Technical Paper | doi.org/10.13182/NSE63-A17388
Measurement of the Neutron Total Cross Section of U233 from 0.07 to 10,000 ev
N. J. Pattenden, J. A. Harvey
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 404-410
Technical Paper | doi.org/10.13182/NSE63-A17389
Monte Carlo Calculations on the Reflection and Transmission of Scattered Gamma Rays
Dominic J. Raso
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 411-418
Technical Paper | doi.org/10.13182/NSE63-A17390
A Semiempirical Formula for Differential Dose Albedo for Gamma Rays on Concrete
A. B. Chilton, C. M. Huddleston
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 419-424
Technical Paper | doi.org/10.13182/NSE63-A17391
Precision Limitations in the Measurement of Small Reactivity Changes
Edgar F. Bennett, Robert L. Long
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 425-432
Technical Paper | doi.org/10.13182/NSE63-A17392
Li(t, n) Be Thick Target Yields
Nelson Jarmie, B. C. Diven
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 433-434
Technical Paper | doi.org/10.13182/NSE63-A17393
The Production of Transuranium Elements
D. E. Ferguson
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 435-437
Technical Paper | doi.org/10.13182/NSE63-A17394
Production of the Transuranium Elements
W. D. Burch, E. D. Arnold, A. Chetham-Strode
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 438-442
Technical Paper | doi.org/10.13182/NSE63-A17395
The High Flux Isotope Reactor
C. E. Winters
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 443-447
Technical Paper | doi.org/10.13182/NSE63-A17396
Chemical Processing Requirements for Transuranium Element Production
R. E. Leuze
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 448-451
Technical Paper | doi.org/10.13182/NSE63-A17397
An Anion Exchange Process for Americium-Curium Recovery from Plutonium Process Waste
M. H. Lloyd
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 452-456
Technical Paper | doi.org/10.13182/NSE63-A17398
Isolation of Transplutonium Elements by Tertiary Amine Extraction
R. D. Baybarz, B. S. Weaver, H. B. Ivinser
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 457-462
Technical Paper | doi.org/10.13182/NSE63-A17399
Separation of Transplutonium Elements by Phosphonate Extraction
R. D. Baybarz
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 463-467
Technical Paper | doi.org/10.13182/NSE63-A17400
Development of Procedures and Equipment for Fabrication of the High Flux Isotope Reactor Target Rods
A. L. Lotts, W. C. Thurber, M. K. Preston, JR., D. A. Douglas, JR
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 468-478
Technical Paper | doi.org/10.13182/NSE63-A17401
Transuranium Processing Facility Design
W. E. Unger, B. F. Bottenfield, F. L. Hannon
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 479-485
Technical Paper | doi.org/10.13182/NSE63-A17402
Evaluation of Shielding and Hazards in the Transuranium Processing Plant
J. P. Nichols, E. D. Arnold, D. K. Trubey
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 486-491
Technical Paper | doi.org/10.13182/NSE63-A17403
Process Equipment Design and Development for Transuranium Processing Plant
O. O. Yarbro, J. L. English, T. S. Mackey
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 492-497
Technical Paper | doi.org/10.13182/NSE63-A17404
Nitrogen Release from UO2 Pellets at Elevated Temperatures
Harry M. Ferrari
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 503-512
Technical Paper | doi.org/10.13182/NSE63-A18440
Time Dependent Neutron Spectra in Graphite
E. Barnard, N. A. Khan, R. C. F. Mclatchie, M. J. Poole, J. H. Tait
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 513-522
Technical Paper | doi.org/10.13182/NSE63-A18441
Design and Test of a Diaphragm Pump for Liquid Metals
D. E. Westerheide, J. C. Clifford, George Burnet
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 523-527
Technical Paper | doi.org/10.13182/NSE63-A18442
Investigations in Spatial Reactor Kinetics
P. T. Hansson, L. R. Foulke
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 528-533
Technical Paper | doi.org/10.13182/NSE63-A18443
Analytic Approximation Techniques
Rubin Goldstein, Harvey Brooks
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 534-536
Technical Paper | doi.org/10.13182/NSE63-A18444
Fission Distribution in Seven-Pin Cluster Fuel Elements
R. Gordon, V. E. Schrock, R. N. Stuart, A. J. Kirschbaum
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 537-546
Technical Paper | doi.org/10.13182/NSE63-A18445
Evaluation of the Doppler-Broadened Single-Level and Interference Functions
T. D. Beynon, I. S. Grant
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 547-550
Technical Paper | doi.org/10.13182/NSE63-A18446
Asymptotic Distribution of Thermal Neutron Flux in an Infinite Medium of Beryllium Containing a Constant Plane Source
R. D. Jain
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 551-556
Technical Paper | doi.org/10.13182/NSE63-A18447
Recovery and Purification of Plutonium by Trilaurylamine Extraction
A. Chesné, G. Koehly, A. Bathellier
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 557-565
Technical Paper | doi.org/10.13182/NSE63-A18448
Recent Solvent Extraction Studies at Hanford Laboratories
R. E. Burns, W. W. Schulz, L. A. Bray
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 566-575
Technical Paper | doi.org/10.13182/NSE63-A18449
Extraction of Sodium and Cesium Polyoidides into Nitrobenzene
L. M. Slater
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 576-585
Technical Paper | doi.org/10.13182/NSE63-A18450
Evaluation of Diethers as Uranium Extractants
J. M. Googin, W. L. Harper, L. R. Phillips, F. W. Postma
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 586-592
Technical Paper | doi.org/10.13182/NSE63-A18451
Purex Process Performance Versus Solvent Exposure and Treatment
D. A. Orth, T. W. Olcott
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 593-612
Technical Paper | doi.org/10.13182/NSE63-A18452
TBP Decomposition Product Behavior in Post-Extractive Operations
H. T. Hahn, E. M. Vander Wall
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 613-619
Technical Paper | doi.org/10.13182/NSE63-A18453
Performance and Degradation of Diluents for TBP and the Cleanup of Degraded Solvents
E. S. Lane
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 620-625
Technical Paper | doi.org/10.13182/NSE63-A18454
Properties of Degraded TBP-Amsco Solutions and Alternative Extractant-Diluent Systems
C. A. Blake, Jr., W. Davis, Jr., J. M. Schmitt
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 626-637
Technical Paper | doi.org/10.13182/NSE63-A18455
Investigations to Determine the Extent of Degradation of TBP/Oderless Kerosene Solvent in the New Separation Plant, Windscale
A. J. Huggard, B. F. Warner
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 638-650
Technical Paper | doi.org/10.13182/NSE63-A18456
