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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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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RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
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.
