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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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!
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Latest News
DNFSB to hold public meeting on aging management
The Defense Nuclear Facilities Safety Board, which provides safety oversight of Department of Energy sites, is holding a public hearing on August 14 on benchmarking of best practices in the management of aging infrastructure.
According to the DNFSB, the goal of the hearing is to gather information from relevant organizations on best practices in infrastructure aging management to inform the development of potential safety improvements to DOE programs.
C. C. Stone, J. A. Ford, F. E. Tippets, J. S. McDonald, G. Grant, J. L. Epstein
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 60-87
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32832
Articles are hosted by Taylor and Francis Online.
The development of sodium-heated steam generators remains a technical challenge after nearly 30 years of design, development, and testing experience in the U.S. Selection of materials, design configurations, and operating conditions have been pursued with the objective of minimizing costs, improving operating efficiencies, and providing increased assurance that high reliability and positive separation of sodium and water can be maintained throughout the operational life of a commercial reactor facility. The early development and operational history of steam generators included the use of both ferritic and austenitic steels, single and double-wall tube construction, straight tubes and tubes with thermal expansion compensation, and once-through and recirculation type of designs. This early work provided the basis for selection of the Clinch River Breeder Reactor Plant (CRBRP) concept in the early 1970s and has since been followed by an active program of steam generator development, with a major effort devoted to determination of material properties as related to structure design and environmental compatibility. A full size CRBRP unit is planned to be tested for verification of the hockey stick design concept. The approach in the U.S. program has gone beyond development, construction, and testing of the CRBRP steam generators to include development of alternate designs for future liquid-metal fast breeder reactor plants. These alternatives include a scaled-up version of the CRBRP hockey stick design, a single-wall helical-coil design, and a doublewall straight-tube design. A program consisting of the design, fabrication, and testing of 70-MW(thermal) prototype models of both the double-wall straight-tube and the single-wall helical-coil concepts is currently under way