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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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.
Krishna Vinjamuri, Richard R. Hobbins
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 145-150
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33213
Articles are hosted by Taylor and Francis Online.
A postirradiation examination of two uranium aluminide (UAlx) fuel plates from the Advanced Test Reactor (ATR) was conducted. The two fuel plates failed due to pinhole corrosion during irradiation to ∼76% of the maximum burnup limit of 2.3 X 1021 fission/cm3. It is believed that the aluminum cladding failed due to pit corrosion initiated at an existing pit ∼0.0076 to 0.0102 cm (3 to 4 mil) deep at a hot spot. About 0.2 and 0.8 g of UAlx fuel was washed out of these plates through the pinholes due to aqueous corrosion and erosion of the UAlx under ATR primary coolant conditions. Aluminum cladding pit corrosion depth and UAlx fuel corrosion-erosion mass rates under the ATR primary coolant conditions were calculated to be 0.23 cm/yr and 14 g/yr, respectively.