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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Investment bill would provide funding options for energy projects
Coons
Moran
The bipartisan Financing Our Futures Act, which expands certain financing tools to all types of energy resources and infrastructure projects, was reintroduced to the U.S. Senate on February 20 by Sens. Jerry Moran (R., Kan.) and Chris Coons (D., Del.).
Via amendment to the Internal Revenue Code, the legislation would allow advanced nuclear energy projects to form as master limited partnerships (MLPs), a tax structure currently available only to traditional energy projects.
An MLP is a business structure that is taxed as a partnership but the ownership interests of which are traded like corporate stock on a market. Until the Internal Revenue Code is amended, MLPs will continue to be available only to investors in energy portfolios for oil, natural gas, coal extraction, and pipeline projects that derive at least 90 percent of their income from these sources. This change would take effect on January 1, 2026.
M. Schad
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 267-288
Technical Paper | Material | doi.org/10.13182/NT80-A32530
Articles are hosted by Taylor and Francis Online.
We investigated whether it is possible to predict corrosion effects for austenitic steels exposed to liquid sodium with an analytical diffusion model The comparison between experimental measurements of corrosion and calculated corrosion effects is described. A diffusion model served as the basis for the calculations. The comparison showed that the analytical model is able to predict the corrosion effects. The diffusion model is based on the observed sodium corrosion characteristics. It includes the upstream history of the sodium as well as the influence of the corroding wall at the considered location. The test loop’s maximum and minimum sodium temperatures were 750°C (1388°F) and 150°C (303°F = cold trap temperature corresponding to 2 to 3 ppm oxygen content), respectively. The cold trap was part of the main circuit. The loop was built of steel 1.4571. The samples were made of steel 1.4571 or 1.4488. The metallographic investigated surfaces were exposed to sodium at temperatures of 500°C (933°F) to 750°C (1383°F) in the heated part of the loop. The comparison between experimental and analytical results shows that the model is able to predict most characteristics of the sodium austenitic corrosion. The analytical results are qualitatively correct and to a fairly good degree quantatively accurate as well. The accuracy of the model predictions depends primarily on the degree of knowledge of the factors determining the diffusion such as the sodium saturation limits and the diffusion coefficient of the individual stainless-steel elements in the corroding wall.