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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Kevin J. Chan, Preet M. Singh
Nuclear Technology | Volume 206 | Number 11 | November 2020 | Pages 1751-1768
Technical Paper | doi.org/10.1080/00295450.2020.1809311
Articles are hosted by Taylor and Francis Online.
Austenitic alloys such as austenitic stainless steels and Ni-based alloys have been specified as container materials for molten salt reactors (MSRs). In MSR environments, these alloys are susceptible to carburization because (1) graphite components provide a source of carbon, (2) oxide films are not protective in molten halide salts, and (3) MSR operating temperatures fall within the temperature range of carbide formation. Carburization may occur simultaneously with corrosion by the selective dissolution of Cr. To study the corrosion behavior of a carburized microstructure, Hastelloy N, Haynes 244, Haynes 230, and Incoloy 800H samples were pre-carburized at 900°C in a hydrocarbon atmosphere prior to exposure to molten FLiNaK at 700°C. Pre-carburized samples featured a carbide-rich microstructure, particularly near the sample surface. The face-centered-cubic matrix of pre-carburized samples was found to be depleted in Cr, Mo, and to a lesser extent W, which are strong carbide-forming elements. Chromium dissolution in pre-carburized samples was suppressed compared to untreated samples due to the reduction in Cr activity. However, selective attack of the connected carbide structure along grain boundaries was observed in pre-carburized Haynes 230 and Incoloy 800H, which are alloys with high Cr content.