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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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DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
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The Age of Polonium-Beryllium Neutrons in Various Metal-Water Mixtures
Melvin Reier, Felix Obenshain, Robert L. Hellens
Nuclear Science and Engineering | Volume 4 | Number 1 | July 1958 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE58-A25515
Neutron Age in Mixtures of D2O and H2O
James W. Wade
Nuclear Science and Engineering | Volume 4 | Number 1 | July 1958 | Pages 12-24
Technical Paper | doi.org/10.13182/NSE58-A25516
The General Critical Reactor Equations
M. J. Nowak
Nuclear Science and Engineering | Volume 4 | Number 1 | July 1958 | Pages 25-43
Technical Paper | doi.org/10.13182/NSE58-A25517
Analysis of Temperatures and Expansions Resulting from Exponential Power Changes in a Reactor
Thomas R. Bump, Ralph W. Seidensticker
Nuclear Science and Engineering | Volume 4 | Number 1 | July 1958 | Pages 44-64
Technical Paper | doi.org/10.13182/NSE58-A25518
Control Rod Worth Studies on Seed and Blanket Reactors
W. H. Hartley, R. T. Bayard
Nuclear Science and Engineering | Volume 4 | Number 1 | July 1958 | Pages 65-72
Technical Paper | doi.org/10.13182/NSE58-A25519
A System of Obtaining and Reducing Neutron Flux Data from a Critical Assembly
H. A. Morewitz, R. F. Valentine
Nuclear Science and Engineering | Volume 4 | Number 1 | July 1958 | Pages 73-81
Technical Paper | doi.org/10.13182/NSE58-A25520
Hydrodynamics of a Liquid Poison Scram System
David Burgreen
Nuclear Science and Engineering | Volume 4 | Number 1 | July 1958 | Pages 82-95
Technical Paper | doi.org/10.13182/NSE58-A25521
Suppression of Neutron-Induced Activation Outside a Hydrogenous Shield
Fritz W. Mezger
Nuclear Science and Engineering | Volume 4 | Number 1 | July 1958 | Pages 96-111
Technical Paper | doi.org/10.13182/NSE58-A25522
Interstitial Compounds of Irradiated Graphite
G. L. Montet
Nuclear Science and Engineering | Volume 4 | Number 1 | July 1958 | Pages 112-133
Technical Paper | doi.org/10.13182/NSE58-A25523
Heat Conduction in Internally Cooled Nuclear Reactors
Roy A. Axford
Nuclear Science and Engineering | Volume 4 | Number 2 | August 1958 | Pages 139-154
doi.org/10.13182/NSE58-A15358
Uranium-235 Neutron Cross Sections from a Breit-Wigner Analysis
Devereux L. Kavanagh
Nuclear Science and Engineering | Volume 4 | Number 2 | August 1958 | Pages 155-165
doi.org/10.13182/NSE58-A15359
Some Applications of the Sn Method
R. M. Klehn
Nuclear Science and Engineering | Volume 4 | Number 2 | August 1958 | Pages 166-179
doi.org/10.13182/NSE58-A15360
The EBR-I Meltdown—Physical and Metallurgical Changes in the Core
J. H. Kittel, M. Novick, R. F. Buchanan
Nuclear Science and Engineering | Volume 4 | Number 2 | August 1958 | Pages 180-199
doi.org/10.13182/NSE58-A15361
The Stability of Multipass Reactors
John Mac Phee
Nuclear Science and Engineering | Volume 4 | Number 2 | August 1958 | Pages 200-208
doi.org/10.13182/NSE58-A15362
An Analytical Approach to the Diffusion Bonding Problem
Louis S. Castleman
Nuclear Science and Engineering | Volume 4 | Number 2 | August 1958 | Pages 209-226
doi.org/10.13182/NSE58-A15363
Fast Neutron Dosimetry in Pile Irradiations
R. Wayne Houston
Nuclear Science and Engineering | Volume 4 | Number 2 | August 1958 | Pages 227-238
doi.org/10.13182/NSE58-A15364
Laminar Tube Flow with Arbitrary Internal Heat Sources and Wall Heat Transfer
E. M. Sparrow, R. Siegel
Nuclear Science and Engineering | Volume 4 | Number 2 | August 1958 | Pages 239-254
doi.org/10.13182/NSE58-A15365
On the Chemistry of the Fission Process in Reactor Fuels Containing UF4 and UO2
Mark T. Robinson
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 263-269
Technical Paper | doi.org/10.13182/NSE58-A25527
Xenon Poisoning Kinetics in Gas-Sparged, Molten Fluoride Fueled Nuclear Reactors
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 270-287
Technical Paper | doi.org/10.13182/NSE58-A25528
The Behavior of Fission Products in Molten Fluoride Reactor Fuels
Mark T. Robinson, William A. Brooksbank, Jr., Samuel A. Reynolds, Henry W. Wright, Thomas H. Handley
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 288-296
Technical Paper | doi.org/10.13182/NSE58-A25529
Determination of k∞ from Critical Experiments with the PCTR
D. J. Donahue, D. D. Lanning, R. A. Bennett, R. E. Heineman
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 297-321
Technical Paper | doi.org/10.13182/NSE58-A25530
Application of the Absorption Area Method To Three-Group Diffusion Theory Problems
S. Pearlstein
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 322-331
Technical Paper | doi.org/10.13182/NSE58-A25531
Effects of Low-Lying Europium Resonances on the Temperature Defect in Water-Moderated Reactors
D. M. Keaveney, T. J. Krieger, M. L. Storm
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 332-340
Technical Paper | doi.org/10.13182/NSE58-A25532
Effect of Alloying on the Critical Mass of a Plutonium Spherical Fast Reactor
James T. Waber, Mary Repar Kline, Leah K. Johnson
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 341-353
Technical Paper | doi.org/10.13182/NSE58-A25533
Broad Aspects of Absorber Materials Selection for Reactor Control
W. K. Anderson
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 357-372
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25534
Nuclear Requirements for Control Materials
H. E. Stevens
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 373-385
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25535
Discrete Fixed Poison Rods Containing Boron
W. E. Ray, W. A. Neisz, H. W. Cooper
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 386-401
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25536
Boron Containing Control Materials
D. N. Dunning, W. K. Anderson, P. R. Mertens
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 402-414
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25537
Boron Stainless Steel Alloys
L. B. Prus, E. S. Byron, J. F. Thompson
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 415-428
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25538
Materials, Fabrication and Performance of the EBWR Control Rods
Nicholas Balai
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 429-438
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25539
The Use of Boron Carbide for Reactor Control
W. K. Barney, G. A. Sehmel, W. E. Seymour
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 439-448
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25540
Development of a Composite Control Rod
G. W. Cunningham, A. K. Foulds, D. L. Keller, W. E. Ray
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 449-457
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25541
Radiation Damage Resistance of Some Rare Earth Cermets
W. K. Anderson, D. N. Dunning
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 458-466
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25542
New Developments in the Fabrication of Hafnium Control Rods
J. Giacobbe, D. N. Dunning
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 467-480
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25543
A Method of Hot Coextruding Complex Shapes through Round Dies
W. E. Ray, C. J. Beck
Nuclear Science and Engineering | Volume 4 | Number 3 | September 1958 | Pages 481-494
Symposium on Reactor Control Materials | doi.org/10.13182/NSE58-A25544
The Preparation of Thorium Metal by Sodium Amalgam Reduction of Thorium Chloride: the Metallex Process
O. C. Dean, G. K. Ellis
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 509-521
Technical Paper | doi.org/10.13182/NSE58-A28827
Mutual Shielding of Lattice Pins in the Resonance Energy Region
W. G. Pettus, I. E. Dayton
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 522-529
Technical Paper | doi.org/10.13182/NSE58-A28828
Self-Shielding Experiments with Gaseous and Solid B-10
G.P. Rutledge, R. R. Eggleston
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 530-535
Technical Paper | doi.org/10.13182/NSE58-A28829
Production Cross Section of N6 and N171
Paul A. Roys, Kalman Shure
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 536-545
Technical Paper | doi.org/10.13182/NSE58-A28830
Age to Indium Resonance for D-D Neutrons in Water
V. Spiegel, Jr., D. W. Oliver, R. S. Caswell
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 546-562
Technical Paper | doi.org/10.13182/NSE58-A28831
Computing Absolute Thermal Neutron Flux from Measurements Made with Indium Foils
Moses A. Greenfield, Roscoe L. Koontz, Alan A. Jarrett
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 563-569
Technical Paper | doi.org/10.13182/NSE58-A28832
A Remark on Neutron Thermalization Theory
G. Leibfried
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 570-575
Technical Paper | doi.org/10.13182/NSE58-A28833
Total Neutron Cross Sections for Structural Materials
R. J. Brown, L. M. Bollinger
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 576-580
Technical Paper | doi.org/10.13182/NSE58-A28834
The Method of Discrete Ordinates
Gerald Goertzel
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 581-587
Technical Paper | doi.org/10.13182/NSE58-A28835
The Kinetics of Circulating Fuel Reactors
John MacPhee
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 588-597
Technical Paper | doi.org/10.13182/NSE4-588-597
Heat Transfer in a Cross Flow Nuclear Reactor
Charles L. Larson
Nuclear Science and Engineering | Volume 4 | Number 5 | November 1958 | Pages 607-622
Technical Paper | doi.org/10.13182/NSE58-A25551
Perturbation Integrals for Two Group Calculations and Application to Reflector Ducts
Gene A. Baraff, Raymond L. Murray, A. C. Menius, Jr.
Nuclear Science and Engineering | Volume 4 | Number 5 | November 1958 | Pages 623-634
Technical Paper | doi.org/10.13182/NSE58-A25552
The General Theory of Control Sheets
Bertram Wolfe
Nuclear Science and Engineering | Volume 4 | Number 5 | November 1958 | Pages 635-648
Technical Paper | doi.org/10.13182/NSE58-A25553
Some Refinements in the Calculation of Resonance Integrals
Jack Chernick, Russel Vernon
Nuclear Science and Engineering | Volume 4 | Number 5 | November 1958 | Pages 649-672
Technical Paper | doi.org/10.13182/NSE58-A25554
Effect of In-Pile Local Boiling on Surface Deposition and Corrosion
Kurt Katz, Walter E. Hopkins, Jr.
Nuclear Science and Engineering | Volume 4 | Number 5 | November 1958 | Pages 673-689
Technical Paper | doi.org/10.13182/NSE58-A25555
Variation of Graphite Diffusion Length with Temperature
R. C. Lloyd, E. D. Clayton, C. R. Richey
Nuclear Science and Engineering | Volume 4 | Number 5 | November 1958 | Pages 690-697
Technical Paper | doi.org/10.13182/NSE58-A25556
Capture and Fission Patterns of U238 in EBR-I (Mark II)
P. Kafalas, R. R. Heinrich
Nuclear Science and Engineering | Volume 4 | Number 5 | November 1958 | Pages 698-702
Technical Paper | doi.org/10.13182/NSE58-A25557
Prompt Neutron Periods of a Critical Assembly Measured with a Pulsed Source
P. J. Bendt, H. J. Karr, F. R. Scott
Nuclear Science and Engineering | Volume 4 | Number 6 | December 1958 | Pages 703-708
doi.org/10.13182/NSE58-A15492
Isotopic Analysis: Cerium-141 and Cerium-144
W. S. Lyon
Nuclear Science and Engineering | Volume 4 | Number 6 | December 1958 | Pages 709-712
doi.org/10.13182/NSE58-A15493
Fission Power Distribution near a Cruciform Water Gap
E. R. Sanford, H. J. Litre
Nuclear Science and Engineering | Volume 4 | Number 6 | December 1958 | Pages 713-726
doi.org/10.13182/NSE58-A15494
Verification of a Method for Treating Neutron Space-Time Problems
A. F. Henry, N. J. Curlee
Nuclear Science and Engineering | Volume 4 | Number 6 | December 1958 | Pages 727-744
doi.org/10.13182/NSE4-727
Plutonium Fast Power Breeder with Oxide Fuel and Blanket Elements
John B. Sampson, E. A. Luebke
Nuclear Science and Engineering | Volume 4 | Number 6 | December 1958 | Pages 745-761
doi.org/10.13182/NSE58-A15496
Selection of a Reactor Containment Structure
Theodore H. Smith, Burr H. Randolph
Nuclear Science and Engineering | Volume 4 | Number 6 | December 1958 | Pages 762-784
doi.org/10.13182/NSE58-A15497
Perturbation Theory of Control Elements. I
Bertram Wolfe, David L. Fischer
Nuclear Science and Engineering | Volume 4 | Number 6 | December 1958 | Pages 785-793
doi.org/10.13182/NSE58-A15498
