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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
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.
A. C. Lingenfelter
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 63-68
A. Selection, Production, and Development of Alloys for HTGR Component | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33455
Articles are hosted by Taylor and Francis Online.
Inconel-618E (54 Ni-23 Cr-6 W) was developed specifically to meet the requirements of the high-temperature gas-cooled reactor (HTGR). The alloy has good fabricability, weldability, and, above all, metallurgical stability. Alloy 618E is free of cobalt and aluminum. At temperatures of 954°C (1750°F) and higher, alloy 618E has stress rupture strength comparable to Inconel-617. At lower temperatures, the rupture strength of alloy 618E is somewhat lower than that of alloy 617. Alloy 617 remains the best-established alloy for HTGR service. However, alloy 618E does not have that material’s disadvantage of aluminum and cobalt content and may become a candidate for HTGR applications.
