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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.