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
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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Jump to:
Study of an Advanced Fuel Handling System
Noriaki Takahashi, Hideaki Morishita, Naomichi Kanegae, Akihiro Niimi
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 7-16
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34275
Reducing Uncertainty Allowance in Core Limits Calculations
John F. Carew
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 17-21
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34276
PRISM: A Safe, Economic, and Testable Liquid-Metal Fast Breeder Reactor Plant
Robert C. Berglund, Frank E. Tippets, Leroy N. Salerno
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 22-29
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34277
In Situ Measurement of Low-Level Radioactivities Using the Compton Suppression Technique
Liq-Ji Yuan, Pao-Shan Weng, Cheng-Chang Chan
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 30-34
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34278
Optimal Success Path Generation System Based on Integrated Reliability Rules
Tae Woon Kim, Sang Hoon Han, Kun Joong Yoo
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 35-39
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34279
Analysis of a Pressurized Water Reactor Natural Circulation Transient at Beginning of Life
Russell D. Mosteller, Peter J. Jensen, Michael J. Anderson,+ Laurance D. Eisenhart, Rana Abdollahian, Jason Chao, Walter J. Eich
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 40-48
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34280
Analysis of a Partial-Refueling Ultra-Long-Life Core Using Metallic Fuel for 1000-MW(electric) Liquid-Metal Fast Breeder Reactors
Katsuyuki Kawashima, Ratib A. Karam
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 49-59
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34281
Partitioning of Nitric Acid Intermediate-Level Waste Solutions by Sorption
Werner Faubel, Sameh A. Ali
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 60-65
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34282
Modeling of the Viscosity of Glasses Used in the Immobilization of High-Level Liquid Nuclear Waste
Elie Saad, Normand Laurent Laberge, Xiangdong Feng
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 66-69
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34283
Identification of Two-Phase Flow Regimes by Neutron Noise Analysis
C. H. King, M. S. Ouyang, B. S. Pei, S. C. Lee
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 70-75
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34284
Gas Tag Blending with Linear Programming
Frank Schmittroth, Miriam A. Myjak
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 76-79
Technical Paper | Technique | doi.org/10.13182/NT89-A34285
The Importance of Collision Efficiency in the Coagulation of Nuclear Aerosol Particles
A. M. Shahub, M. M. R. Williams
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 80-86
Technical Note | Nuclear Safety | doi.org/10.13182/NT89-A34286
The International Atomic Energy Agency’s Program on Decontamination and Decommissioning
Melville A. Feraday
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 99-110
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34260
The Windscale Advanced Gas-Cooled Reactor Stage 3 Decommissioning Project
Philip J. Thomas, Tim Boorman
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 111-119
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34261
Decommissioning a 60-m-Tall Exhaust Stack
Robert L. Louie, Dwayne R. Speer
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 120-127
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34262
Dismantling the RB-2 Research Reactor: An Application of a Radiation Protection Approach Relevant to Italy’s Decommissioning Methodology
Michele Laraia, Giuseppe Brighenti, Bartolomeo Camiscioni, Giovanni Chessa
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 128-135
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34263
Decontamination of Three Mile Island Unit 2
Michael D. Pavelek II, Joann S. Epler, Robert J. Vallem
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 136-147
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34264
Dismantling Techniques for Reactor Steel Structures
Satoshi Yanagihara, Yoshihiro Seiki, Hisashi Nakamura
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 148-158
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34265
Dismantling Techniques for Reactor Steel Piping
Satoshi Yanagihara, Fujio Hiraga, Hisashi Nakamura
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 159-167
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34266
Cutting Technique and System for Biological Shield
Hisashi Nakamura, Toshimasa Narazaki, Satoshi Yanagihara
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 168-178
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34267
Dismantling by Explosives
Hans Ulrich Freund, Klaus Müller
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 179-187
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34268
Results of Melting Large Quantities of Radioactive Steel Scrap
Manfred Sappok
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 188-191
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34269
Behavior of Actinides and Other Difficult to Measure Radionuclides in the Melting of Contaminated Steel
Eberhard Schuster, Kurt A. Pflugrad
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 192-196
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34270
Preliminary Studies of Packaging and Disposal of Decommissioning Waste in Switzerland
Jean-Claude Alder
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 197-206
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34271
Deep-Bed Fiberglass Filter Assembly Radiological Characterization
Vishnu B. Subrahmanyam, Dwayne R. Speer
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 207-213
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34272
Present Status of Fast Breeder Reactor Development in Japan
Sadamu Sawai, Yonesuke Iwakoshi
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 219-232
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34290
Codes and Standards for Fast Breeder Reactor Components—A European Point of View
Roland L. Roche, C. H. A. Townley, Kurt Vinzens, H. Laue, Franco Corsi, M. De Bacci
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 233-238
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34291
Defective Fuel Rod Detection in Operating Pressurized Water Reactors During Periods of Continuously Decreasing Fuel Rod Integrity Levels
Harald Zänker
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 239-247
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34292
Low-Enriched Uranium Conversion/Power Upgrade of The Ohio State University Research Reactor
Tunc Aldemir, Joseph W. Talnagi,*, Don W. Miller
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 248-263
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34293
Fast Flux Test Facility Fuel Handling Experience—November 1979 to August 1988
Delwin M. Romrell, Don M. Art, Richard D. Redekopp, James B. Waldo, Jerry L. Marshall
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 264-274
Technical Paper | Fuel Cycle | doi.org/10.13182/NT89-A34294
An Improvement in the Use of Plutonium in Pressurized Water Reactors: The Subassembly Mixed-Oxide Fuel Management Concept
Corinne Bangil, Gérard Gambier, Michel Soldevila
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 275-281
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34295
Equilibrium Time and Criticality Considerations in Uranium Enrichment by the Chemical-Exchange Process
Yasuhiko Fujii, Makoto Okamoto, Hiroyuki Kadotani, Hidetake Kakihana
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 282-288
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34296
Increased-Discharge-Burnup Method for Multicycle Reload Design
Hyong Chol Kim, Ming-Yuan Hsiao, Samuel H. Levine
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 289-304
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34297
Long-Term Isolation of High-Level Radioactive Waste in Salt Repositories Containing Brine
Donald G. Schweitzer, Cesar A. Sastre
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 305-312
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34298
