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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
M. R. Fox, A. B. Hull, T. F. Kassner
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1619-1628
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29573
Articles are hosted by Taylor and Francis Online.
Susceptibility of Types 316NG, 316, and 304 stainless steels (SS) to stress corrosion cracking was investigated in slow-strain-rate tests (SSRTs) in oxygenated water that simulates important parameters anticipated in first-wall/blanket systems. The water chemistry was based on a computer code that yielded the nominal concentrations of radiolytic species produced in an aqueous environment under conditions expected in the International Thermonuclear Experimental Reactor (ITER). Actual SSRTs were performed in a less benign, more oxidizing reference environment at temperatures of 52 to 150°C. Predominantly ductile fracture was observed in Type 316NG and nonsensitized Types 316 and 304 SS SSRT specimens that were strained to failure in a reference ITER water chemistry. The failure behavior of Type 304 SS specimens, heat-treated to yield sensitization values of 2, 3, and 20 Coulomb (C)/cm2 by the electrochemical potentiokinetic reactivation technique, demonstrated that the degree of sensitization dramatically affected susceptibility to intergranular stress corrosion cracking. Ranking for resistance to stress corrosion cracking in simulated ITER water by electron microscopy and SSRT parameters, i.e., failure time, ultimate strength, total elongation, and stress ratio, is 304 SS (EPR = 20<2 C/cm2)<316NG SS.