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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
James R. Lindgren
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 607-618
G. Irradiation Behavior | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33482
Articles are hosted by Taylor and Francis Online.
A preliminary study has been completed on how irradiation affects structural materials of high-temperature gas-cooled reactor (HTGR) steam cycle/ cogeneration plant components. A literature search was conducted on irradiation data available for reactor component materials, and results are summarized. Data on materials for the core lateral restraint, core peripheral seal, thermal barriers, and control/power rods are reviewed. Irradiation data on the metals (lowalloy carbon steel, Hastelloy alloy X, alloy 800, and Inconel-718) and on the ceramics (alumina and silica) indicate no major changes on the tensile or creep strengths of the materials occurring at fluences that exceed those found in the HTGR, which are expected to be 1 x 1017 n/cm2 fast and 1 x 1017 n/cm2 thermal. Ductility of most of the metals is significantly reduced and this reduction needs to be considered in design of the components exposed to irradiation. Future work on irradiation effects studies will be focused on the high cycle fatigue behavior of the metals since those data are not yet available. The effects of irradiationinduced creep on the stress relaxation of Inconel-718 core lateral restraint springs also need to be determined.