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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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.
John P. Foster, Robert V. Strain
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 93-98
Technical Note | Material | doi.org/10.13182/NT74-A31464
Articles are hosted by Taylor and Francis Online.
Bilinear and power law swelling equations were developed for solution-annealed Type 304 stainless steel from Treat Tubing heat 136272. All of the temperatures and fluences were calculated with the same thermal-hydraulic computer code. This procedure insured that all the data were evaluated on a consistent basis. The swelling equations formulated in this investigation were different from other empirical equations because of differences in the swelling data and the form of the swelling equation. The bilinear equation is recommended for the analysis of experimental data and will be used in the analysis of residual stress measurements made on the same lot of tubing.
