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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
G. P. Airey, A. R. Vaia, R. G. Aspden
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 436-448
Technical Paper | Materials | doi.org/10.13182/NT55-436
Articles are hosted by Taylor and Francis Online.
Inconel 690 is an austenitic nickel base alloy that has been considered for use as steam generator tubing in pressurized water reactors. It has a composition comparable to the currently used Inconel 600 apart from a higher chromium content (30%). Inconel 690 was evaluated for stress corrosion cracking (SCC) resistance in deaerated sodium hydroxide solutions and all-volatile treatment (AVT) environments, and the results are compared with those from thermally treated Inconel 600. The effect of such metallurgical variables as grain size and thermal treatment on SCC resistance was investigated. The caustic SCC resistance of Inconel 690 was significantly improved, compared to the mill-annealed product, when thermally treated over a wide range of temperatures [649 to 871°C (1200 to 1600°F)] and times (1 to 30 h). The SCC resistance of thermally treated Inconel 690 was found to be excellent when exposed to deaerated sodium hydroxide at 343°C (650°F) and 316°C (600°F). There was an increase in caustic SCC susceptibility with decreasing grain size in mill-annealed tubing. However, the corresponding thermally treated tubing showed no caustic SCC susceptibility. No evidence of SCC degradation has been found in either mill-annealed or thermally treated Inconel 690 exposed to high temperature AVT and “pure water” environments.