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Division Spotlight
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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Latest News
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.
A. J. Lovell
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 323-331
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31198
Articles are hosted by Taylor and Francis Online.
The effects of fast reactor irradiation on the creep behavior of annealed Type 316 stainless steel were reviewed and the interrelation between creep response and irradiation-induced microstructure development was analyzed. The effects of neutron fluence, irradiation temperature, and test temperature on creep response were studied using illustrative examples. The results indicate that use of creep data from unirradiated specimens for design purposes over estimates strain expected during irradiation, except when a component is stressed at low temperature following high temperature irradiation.
