ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Jump to:
Determination of the Neutron Temperature at the Center of the Thermal Test Reactor
G. B. Gavin
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 1-13
doi.org/10.13182/NSE57-A15567
Heat Transfer and Economic Considerations for Selecting Core Sizes and Configurations
R. E. Behmer, B. L. Hoffman
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 14-23
doi.org/10.13182/NSE57-A15568
A Direct Measurement of the Uranium Metal Temperature Coefficient of Reactivity
R. M. Pearce, D. H. Walker
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 24-32
doi.org/10.13182/NSE57-A15569
The Neutron Fissionability of U-239 and Th-233
P. R. Fields, G. L. Pyle, W. C. Bentley
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 33-37
doi.org/10.13182/NSE57-A15570
Mechanism of Dimensional Instability of Uranium
L. L. Seigle, A. J. Opinsky
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 38-48
doi.org/10.13182/NSE57-A15571
Fast Neutron Damaging in Nuclear Reactors. I. Radiation Damage Monitoring with the Electrical Conductivity of Graphite
W. Primak, L. H. Fuchs
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 49-56
doi.org/10.13182/NSE57-A15572
The Preparation of Anhydrous Thorium Tetrachloride
O. C. Dean, J. M. Chandler
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 57-72
doi.org/10.13182/NSE57-A15573
Transient Conduction in Nuclear Reactor Fuel Elements
Lloyd G. Alexander
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 73-86
doi.org/10.13182/NSE57-A15574
Neutron Temperature Measurements in Graphite
M. Küchle
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 87-95
doi.org/10.13182/NSE57-A15575
Experimental Study of Transient Behavior in a Subcooled, Water-Moderated Reactor
F. Schroeder, S. G. Forbes, W. E. Nyer, F. L. Bentzen, G. O. Bright
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 96-115
doi.org/10.13182/NSE57-A15576
Fast Neutron Damaging in Nuclear Reactors. II. The Radiation Damage Function of Graphite
W. PRIMAK
Nuclear Science and Engineering | Volume 2 | Number 2 | April 1957 | Pages 117-125
Technical Paper | doi.org/10.13182/NSE57-A25381
Radioactive Carry-Over from Borax-III and Test Systems
ARTHUR J. SHOR, HENRY T. WARD, DAVID MILLER, WALTON A. RODGER
Nuclear Science and Engineering | Volume 2 | Number 2 | April 1957 | Pages 126-142
Technical Paper | doi.org/10.13182/NSE57-A25382
Attenuation of 14.1-Mev Neutrons in Water
R. S. CASWELL, R. F. GABBARD, D. W. PADGETT, W. P. DOERING
Nuclear Science and Engineering | Volume 2 | Number 2 | April 1957 | Pages 143-159
Technical Paper | doi.org/10.13182/NSE57-A25383
Engineering Data for Diphenyl Cooled Nuclear Reactors
L. W. FROMM , KERMIT ANDERSON
Nuclear Science and Engineering | Volume 2 | Number 2 | April 1957 | Pages 160-169
Technical Paper | doi.org/10.13182/NSE57-A25384
Spatial Distribution of Thermal Neutrons from an N17 Source in Water
KALMAN SHURE, PAUL A. ROYS
Nuclear Science and Engineering | Volume 2 | Number 2 | April 1957 | Pages 170-180
Technical Paper | doi.org/10.13182/NSE57-A25385
Measurement of Local Heat Transfer Coefficients with Sodium-Potassium Eutectic in Turbulent Flow
K. D. KUCZEN, T. R. BUMP
Nuclear Science and Engineering | Volume 2 | Number 2 | April 1957 | Pages 181-198
Technical Paper | doi.org/10.13182/NSE57-A25386
Neutron Thermalization: II. Heavy Crystalline Moderator
MARK NELKIN
Nuclear Science and Engineering | Volume 2 | Number 2 | April 1957 | Pages 199-212
Technical Paper | doi.org/10.13182/NSE57-A25387
Thermal Stresses in Clad Fuel Plates
CHARLES O. SMITH
Nuclear Science and Engineering | Volume 2 | Number 2 | April 1957 | Pages 213-218
Technical Paper | doi.org/10.13182/NSE57-A25388
The Neutron Velocity Spectrum in a Heavy Moderator1
E. RICHARD COHEN
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 227-245
Technical Paper | doi.org/10.13182/NSE57-A25393
Measuring the Ratio of Thermal to Resonance Neutron Densities Using Thick Indium Foils1
MOSES A. GREENFIELD, ROSCOE L. KOONTZ, ALAN A. JARRETT
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 246-252
Technical Paper | doi.org/10.13182/NSE57-A25394
Criticality and Flux Calculations for Hydrogenous Assemblies
N. C. FRANCIS, H. HURWITZ, JR., P. F. ZWEIFEL
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 253-287
Technical Paper | doi.org/10.13182/NSE57-A25395
Calibration of Control Rods1
F. J. JANKOWSKI,2 D. KLEIN, T. M. MILLER
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 288-302
Technical Paper | doi.org/10.13182/NSE57-A25396
The Use of Fluidized Beds for the Continuous Drying and Calcination of Dissolved Nitrate Salts
A. A. JONKE, E. J. PETKUS, J. W. LOEDING, AND S. LAWROSKI
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 303-319
Technical Paper | doi.org/10.13182/NSE57-A25397
Fast Neutron Damaging in Nuclear Reactors. III. The Radiation Damage Dosage1
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 320-333
Technical Paper | doi.org/10.13182/NSE57-A25398
Statistical Evaluation of Fission-Product Absorption Cross Sections at Intermediate and High Energies
P. GREEBLER,† H. HURWITZ, JR.,†† M. L. STORM
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 334-351
Technical Paper | doi.org/10.13182/NSE57-A25399
Method of Studying Multi-Region Reactors with an Analog Computer
J. G. BAYLY, R. M. PEARCE
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 352-362
Technical Paper | doi.org/10.13182/NSE57-A25400
Delayed-Neutron Monitors for the Detection of Sheath Failures in Reactor Fuel Rods
C. H. MILLAR, B. W. SARGENT,1 J. C. HORSMAN
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 363-372
Technical Paper | doi.org/10.13182/NSE57-A25401
The Thermal Spectrum of an Intermediate Assembly
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 373-381
Technical Paper | doi.org/10.13182/NSE57-A25402
Reactors, Hazard vs Power Level
THOMAS J. BURNETT
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 382-393
Technical Paper | doi.org/10.13182/NSE57-A25403
The Wigner-Wilkins Calculated Thermal Neutron Spectra Compared with Measurements in a Water Moderator
HARVEY J. AMSTER
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 394-404
Technical Paper | doi.org/10.13182/NSE57-A25404
Refining of Uranium
Bernhard Blumenthal
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 407-426
Technical Paper | doi.org/10.13182/NSE57-A25406
Half-Lives of Radionuclides. I
H. W. Wright, E. I. Wyatt, S. A. Reynolds, W. S. Lyon, T. H. Handley
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 427-430
Technical Paper | doi.org/10.13182/NSE57-A25407
Effects of Irradiation on Some Corrosion-Resistant Fuel Alloys
J. H. Kittel, S. Greenberg, S. H. Paine, J. E. Draley
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 431-449
Technical Paper | doi.org/10.13182/NSE57-A25408
Prompt Neutron Periods of Metal Critical Assemblies
John D. Orndoff
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 450-460
Technical Paper | doi.org/10.13182/NSE57-A25409
Application of Minimum Loading Conditions to Enriched Lattices
P. L. Hofmann, H. Hurwitz, Jr.
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 461-468
Technical Paper | doi.org/10.13182/NSE57-A25410
Oscillations in the Power Distribution within a Reactor1
A. F. Henry, J. D. Germann
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 469-480
Technical Paper | doi.org/10.13182/NSE57-A25411
On the Effective Capture Cross Section of Pu-240 for Reactor Neutrons
R. W. Stoughton, J. Halperin
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 481-487
Technical Paper | doi.org/10.13182/NSE57-A25412
Resonance Absorption of Neutrons in Metal and Oxide Cylinders
Monte V. Davis
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 488-491
Technical Paper | doi.org/10.13182/NSE57-A25413
Radiation-Induced Decomposition of Thorium Nitrate Solutions
J. W. Boyle, H. A. Mahlman
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 492-500
Technical Paper | doi.org/10.13182/NSE57-A25414
UO2-NaK Slurry Studies in Loops to 600°C
B. M. Abraham, H. E. Flotow, R. D. Carlson
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 501-512
Technical Paper | doi.org/10.13182/NSE57-A25415
Radiation-Induced Hardness Changes in Graphite
K. E. Horton, R. L. Carter
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 513-515
Technical Paper | doi.org/10.13182/NSE57-A25416
Measurements with a Pulsed Neutron Source
K. H. Beckurts
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 516-522
Technical Paper | doi.org/10.13182/NSE57-A25417
Natural Circulation Steam Generators for Nuclear Power Plants
J. C. Westmoreland
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 533-546
Technical Paper | doi.org/10.13182/NSE57-A25423
Heat Transfer in Fully Developed Flow between Parallel Plates with Variable Heat Sources
Albert L. Loeffler, Jr.
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 547-566
Technical Paper | doi.org/10.13182/NSE57-A25424
Estimation of Fission Product Spectra in Discharged Fuel from Fast Reactors
Ira G. Dillon and Leslie Burris, Jr.
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 567-581
Technical Paper | doi.org/10.13182/NSE57-A25425
Preliminary Design of an LMFR Power Plant
D. Mars, J. N. Inglima, and R. T. Schomer
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 582-601
Technical Paper | doi.org/10.13182/NSE57-A25426
Nondestructive Testing of Reactor Fuel Elements
W. J. McGonnagle
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 602-616
Technical Paper | doi.org/10.13182/NSE57-A25427
Multiple Scattering of Neutrons
G. W. Stuart
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 617-625
Technical Paper | doi.org/10.13182/NSE57-A25428
Monte Carlo Calculation of the Slowing-Down Time Distribution for Neutrons in Hydrogen
George E. Haynam, Marshall F. Crouch
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 626-630
Technical Paper | doi.org/10.13182/NSE57-A25429
Experimental Measurement of the Slowing-Down Time Distribution for Neutrons in Water
Marshall F. Crouch
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 631-639
Technical Paper | doi.org/10.13182/NSE57-A25430
An Experimental Study of Transient Boiling
M. W. Rosenthal
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 640-656
Technical Paper | doi.org/10.13182/NSE57-A25431
Determination of the Ratio of Capture to Fission Cross Sections in EBR-I
P. Kafalas, M. Levenson, C. M. Stevens
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 657-663
Technical Paper | doi.org/10.13182/NSE57-A25432
The Chemical Processing of Two-Region Aqueous Homogeneous Reactors
D. E. Ferguson
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 664-675
Technical Paper | doi.org/10.13182/NSE57-A25433
Resonance Escape Probability Measurements in Th-2% U-235 Light-Water Moderated Lattices
J. P. Phelps, R. Sher
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 676-678
Technical Paper | doi.org/10.13182/NSE57-A25434
Experimental Estimate of the Free Energy of Formation of Plutonium Trifluoride
A. G. Buyers, E. W. MURBACH
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 679-686
Technical Paper | doi.org/10.13182/NSE57-A25435
A General Treatment of Flux Transients
H. D. Brown
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 687-693
Technical Paper | doi.org/10.13182/NSE57-A25436
Transient Pressures in Nuclear Reactors
J. A. Fleck, Jr.
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 694-708
Technical Paper | doi.org/10.13182/NSE57-A25437
Instrumentation in Aircraft for Radiation Measurements
F. J. Davis, P. W. Reinhardt
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 713-727
Technical Paper | doi.org/10.13182/NSE57-A35487
Calculation of Thermal Group Constants for Mixtures Containing Hydrogen
C. D. Petrie, M. L. Storm, P. F. Zweifel
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 728-744
Technical Paper | doi.org/10.13182/NSE57-A35488
Neutron Age in Diphenyl
N. C. Francis, M. L. Storm, P. F. Zweifel
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 745-747
Technical Paper | doi.org/10.13182/NSE57-A35489
Stored Energy in Neutron-Bombarded Graphite
T. J. Neubert, R. B. Lees
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 748-767
Technical Paper | doi.org/10.13182/NSE57-A35490
Uranium Recovery for Spent Fuel by Dissolution in Fused Salt and Fluorination
G. I. Cathers
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 768-777
Technical Paper | doi.org/10.13182/NSE57-A35491
The Diffusion of Uranium into Aluminum
T. K. Bierlein, D. R. Green
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 778-786
Technical Paper | doi.org/10.13182/NSE57-A35492
The Interaction of 0.15- to 1.0-Mev Neutrons with U-238, U-235, and Pu-239
Robert C. Allen
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 787-793
Technical Paper | doi.org/10.13182/NSE57-A35493
Molten Fluorides as Power Reactor Fuels
R. C. Briant, Alvin M. Weinberg
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 797-803
Technical Paper | doi.org/10.13182/NSE57-A35494
The Aircraft Reactor Experiment—Design and Construction
E. S. Bettis, R. W. Schroeder, G. A. Cristy, H. W. Savage, R. G. Affel, L. F. Hemphill
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 804-825
Technical Paper | doi.org/10.13182/NSE57-A35495
The Aircraft Reactor Experiment—Physics
W. K. Ergen, A. D. Callihan, C. B. Mills, Dunlap Scott
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 826-840
Technical Paper | doi.org/10.13182/NSE57-A35496
The Aircraft Reactor Experiment—Operation
E. S. Bettis, W. B. Cottrell, E. R. Mann, J. L. Meem, G. D. Whitman
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 841-853
Technical Paper | doi.org/10.13182/NSE57-A35497
ANS NEWS
W. W . Grigorieff
Nuclear Science and Engineering | Volume 2 | Number 6 | November 1957 | Pages 854-855
doi.org/10.13182/NSE57-A35498
