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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.
M. Grounes
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 228-235
Technical Paper and Note | doi.org/10.13182/NT68-A28024
Articles are hosted by Taylor and Francis Online.
The susceptibility to irradiation effects in different heats of the same steel and in parts of a reactor vessel that had gone through different stages in the manufacturing process was investigated. Fourteen sets of miniature impact specimens of Uddeholm UHB 2103/R3 steel, the pressure vessel material of the Ågesta reactor, were irradiated at 235 ± 15°C to a neutron fluence of 4 × 1018 − 1019 n/cm2 (>1 MeV). The results indicate that there might be a difference by a factor of 2 in irradiation-induced transition temperature increases between materials from different parts of the vessel. Generally, changes in the hot-pressed material seemed to be larger. If irradiation-damage studies are performed on flat, normalized plate, the results are valid if an extra safety margin of 30°C is applied.