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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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.
M. D. Fitzsimmons, W. L. Pearl, M. Siegler
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 18-29
Technical Paper | doi.org/10.13182/NSE63-A17206
Articles are hosted by Taylor and Francis Online.
A versatile boiling water and superheated steam facility has been developed for out-of-pile corrosion testing of materials that are being used and considered for application in boiling water reactor (BWR) and superheat reactor (SHR) systems. The following capabilities have been achieved: 1. Simulation of the various environments (other than irradiation) that would contact materials in a Dresden type BWR and an SHR utilizing steam generated therefrom. Test space is available at 1000 psi in saturated steam, steam-water mixture and saturated water at 546°F and in superheated steam at 1050°F. 2. Dynamic fuel-cladding material tests operated with a heat flux of 250,000 Btu/hr-ft2 for testing tubular type cladding under representative BWR heat transfer conditions. 3. Dynamic fuel-cladding-material tests operated with a heat flux of 170,000 Btu/hr-ft2 for testing tubular cladding under representative SHR heat-transfer conditions. 4. Control of oxygen and hydrogen content in the steam and water to simulate the gas conditions from radiolytic water decomposition found in a BWR. 5. Attainment of metal temperatures of 1300°F while superheating steam to 1050°F.
