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The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
D. W. LaBelle
Nuclear Technology | Volume 10 | Number 4 | April 1971 | Pages 454-459
Technical Paper | Symposium on Reactor Containment Spray System Technology / Reactor | doi.org/10.13182/NT71-A16256
Articles are hosted by Taylor and Francis Online.
Since all materials of construction are not compatible with spray solutions, an additional problem must be resolved. The corrosion of aluminum and zinc fabricated or coated components in a typical PWR plant when contacted with the sodium hydroxide in the alkaline sodium thiosulfate spray solution is a major contributor to post-accident hydrogen generation. When the hydrogen from metals corrosion is combined with the hydrogen generated from radiolytic decomposition of the coolant and the Zircaloy-water reaction of the overheated fuel cladding, hydrogen can reach a flammable concentration level in the reactor building within 1 to 2 months after a LOCA.