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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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.
