ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Nuclear Science and Engineering
July 2025
Nuclear Technology
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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Peter K. Mast, James H. Scott
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 600-605
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32371
Articles are hosted by Taylor and Francis Online.
A new fuel pin failure model, the Los Alamos Failure Model (LAFM), based on a linear life fraction rule failure criterion, has been developed to provide a reliable and inexpensive prediction of the time and axial location of liquid-metal fast breeder reactor fuel pin failure in a hypothetical transient overpower (TOP) accident. Code testing analyses for a number of TOP Transient Reactor Test Facility tests have resulted in excellent agreement between calculated and observed pin failure time and location. Because of the nature of the failure criterion used, the code has also been used to investigate the extent of cladding damage incurred in terminated as well as unterminated TOP transients in the fast test reactor. The results of these analyses show that 3 dollar/s and 50 and 5 cent/s transients terminated by the secondary trip point (25% overpower) result in negligible calculated cladding damage.