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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Jump to:
Nuclear Power Plant Site Selection: A Case Study
Yaakoy Lugasi, Abraham Mehrez, Zilla Sinuany-Stern
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 7-13
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33590
Improvements in Compartment Fire Modeling and Simulation of Experiments
Gary Chung, Nathan Siu, George Apostolakis
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 14-26
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33591
Sensitivity and Uncertainty Analyses for the Accident Sequence Precursor Study
Mohammad Modarres, Theodore W. Cadman, Erasmia Lois, Alan R. Gardner
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 27-35
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33592
Radioactive Source Term Models in a Compartment Fire Code
Marcel Y. Ballinger, Peter C. Owczarski
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 36-43
Technical Paper | Fuel Cycle | doi.org/10.13182/NT85-A33593
Status of Qualification of High-Temperature Reactor Fuel Element Spheres
Werner Heit, Hans Huschka, Wilhelm Rind, Günter G. Kaiser
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 44-54
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33594
Behavior of Breached Light Water Reactor Spent Fuel Rods in Air and Inert Atmospheres at 229°C
Robert E. Einziger, James A. Cook
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 55-71
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33595
Measurement of Cladding Temperatures with Loss-of-Fluid-Test Thermocouples in the COSIMA Blowdown Test Facility
Gottfried Class, Klaus Hain, Rainer Meyder
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 72-81
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33596
An Experimental Study of Rod Bundle Dispersed-Flow Film Boiling with High-Pressure Water
David G. Morris, Charles B. Mullins, Graydon L. Yoder, Jr.
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 82-93
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33597
An Empirical Mixing Model for Pressurized Thermal Shock Applications
V. K. (Bindi) Chexal, Jason Chao, Robert E. Nickell, Timothy J. Griesbach
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 94-99
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33598
Assessment of TRAC Codes with Dartmouth College Countercurrent Flow Tests
U. S. Rohatgi
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 100-106
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33599
Development of a New Measurement Method for Fast Breeder Reactor Fuel Burnup Using a Shielded lon Microprobe Analyzer
Mineo Mizuno, Yuji Enokido, Ichiro Unno, Keiichi Kono, Sadamu Yamanouchi, Toshiyuki Itaki
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 107-113
Technical Paper | Technique | doi.org/10.13182/NT85-A33600
Initial Results for the Experimental Evaluation of a Nuclear Waste Repository Source Term Model
B. P. McGrail, L. A. Chick, G. L. McVay
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 114-118
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT85-A33601
Gas Core Reactor Neutronics —Theoretical Modeling and Experimental Verification
Edward T. Dugan, Nils J. Diaz, Edward E. Carroll, Jr., H. M. Forehand
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 134-153
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33625
A Study of Corrosion-Resistant Materials for Pulsed Gaseous Core Nuclear Systems
E. Dow Whitney, Dae Joon Kim, Dennis S. Tucker+
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 154-160
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33626
Thermophysical Properties of UF6-He Mixtures Relevant to Circulating Gas Core Reactor Systems
Calvin C. Oliver, Edward T. Dugan
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 161-169
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33627
Transfer of Molecular Fission Products Between a Gas and a Surface, with Application to Iodine Retention in a Granular Bed
Hans S. Häggblom
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 170-177
Nuclear Safety | doi.org/10.13182/NT85-A33628
Decontamination of Carbonate Containing Process Streams in Nuclear Fuel Reprocessing by Ion Exchange Chromatography
Werner Faubel, Sameh A. AL
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 178-185
Chemical Processing | doi.org/10.13182/NT85-A33629
The Behavior of Breached Boiling Water Reactor Fuel Rods on Long-Term Exposure to Air and Argon at 598 K
R. Kohli, D. Stahl, V. Pasupathi, A. B. Johnson, Jr., E. R. Gilbert
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 186-197
Nuclear Fuel | doi.org/10.13182/NT85-A33630
FCODE-BETA/SS: A Fuel Performance Code for Stainless Steel Clad Pressurized Water Reactor Fuel
Richard W. Smith, Gary S. Was
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 198-209
Nuclear Fuel | doi.org/10.13182/NT85-A33631
Subchannel Analysis Program for Boiling Water Reactor Fuel Bundles Based on Five Conservation Equations of Two-Phase Flow
Yasunori Bessho, Sadao Uchikawa
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 210-217
Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33632
Multiregion Concentration Diffusion Coefficient Determination Using Davidon’s Variable Metric Method
Clarence E. Lee, Joe W. Durkee
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 218-235
Analyse | doi.org/10.13182/NT85-A33633
The International DEMO-RAMP-II Project at Studsvik
H. Mogard, H. Knaab, U. Bergenlid, G. Lysell
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 236-242
Technical Note | Nuclear Fuel | doi.org/10.13182/NT85-A33634
Radiation Levels During Shutdown in Boiling Water Reactors
M. J. Hazzan, M. S. Stocknoff, David W. Barcomb, Timothy Irving
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 249-256
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33608
Three-Dimensional Calculations of Fluid-Thermal Mixing in a Babcock & Wilcox Plant at Stagnated Loop Flow
Yassin A. Hassan
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 257-267
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33609
Convective Cooling of Simulated Core Debris Beds
H. S. Kim, S. I. Abdel-Khalik
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 268-278
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33610
Radiation Transport in a Liquid-Metal Fast Breeder Reactor During a Loss of Sodium Coolant Reactor Core Disassembly
Douglas J. Rzepecki
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 279-292
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33611
Availability of the Emergency Core Cooling System of a CANDU Pressurized Heavy-Water Reactor Following a Small Loss-of-Coolant Accident
Tawfik A. Al-Kusayer
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 293-307
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33612
Circulation within the Primary System at TMI-2 with Lowered Coolant Level and at Atmospheric Conditions
V. F. Baston, K. J. Hofstetter, A. P. Malinauskas
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 308-318
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33613
Gravitational Collision Efficiency of Nonspherical Aerosols I: Definitions of Shape Factors
Ronald F. Tuttle, Sudarshan K. Loyalka
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 319-326
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33614
Gravitational Collision Efficiency of Nonspherical Aerosols II: Motion of an Oblate Spheroid in a Viscous Fluid
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 327-336
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33615
Gravitational Collision Efficiency of Nonspherical Aerosols III: Computer Program NGCEFF and Calculation of Shape Factors
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 337-349
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33616
Fuel Management and Core Design Code Systems for Pressurized Water Reactor Neutronic Calculations
Carol Ahnert, José M. Aragonés
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 350-367
Technical Paper | Fuel Cycle | doi.org/10.13182/NT85-A33617
Migration Behavior of Fission Products in and from Spherical High-Temperature Reactor Fuel Elements
Kousaku Fukuda, Ekkehard Groos, John Rau
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 368-379
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33618
Plutonium, Americium, and Neptunium Speciation in Selected Groundwaters
Jess M. Cleveland, Terry F. Rees, Kenneth L. Nash
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 380-387
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33619
Transient Two-Phase Blowdown Predictions of an Initially Stagnant Saturated Liquid Steam in a Vessel Using TRAC-PF1
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 388-392
Technical Note | Fission Reactor | doi.org/10.13182/NT85-A33620
Proton Dosimeter Design for Distributed Body Organs
John W. Wilson, Govind S. Khandelwal
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 393-394
Technical Note | Technique | doi.org/10.13182/NT85-A33621
