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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.
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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.
R. P. Schuman
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 254-264
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32852
Articles are hosted by Taylor and Francis Online.
A number of pellets and highly durable glasses, prepared from nonradioactive simulated high-level waste calcines, have been leach tested. The leach tests were patterned on the International Atomic Energy Agency standard test and the proposed Materials Characterization Center tests. Most tests were made with static distilled water at 25, 70, 95, 250, and 350°C and in refluxing distilled water at 95°C. Leach rates were determined by analyzing the leachate by instrumental activation analysis or spectrochemical analysis and from weight loss. The leach tests were run on solid pieces of glass (cast and core-drilled cylinders and broken pieces) and on coarse ground glass. Solid pieces gave higher leach rates than ground glass. Cesium, molybdenum, sodium, and weight loss leach rates of solid pieces of glass in distilled water were comparable and varied from <10-7 g/cm2 day at 25°C to ∼10-1 g/cm2 day at 250°C. The leach rates in static distilled water at 95°C were lower than those in refluxing distilled water at the same temperature. Even at 25°C, sodium, cesium, and molybdenum readily leached from the porous pellets, but the pellets showed no visible attack, even at 250°C.