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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
Hermann J. Möckel, Rainer H. Köster
Nuclear Technology | Volume 59 | Number 3 | December 1982 | Pages 494-497
Technical Paper | The Backfill as an Engineered Barrier for Radioactive Waste Management / Radioactive Waste Management | doi.org/10.13182/NT82-A33007
Articles are hosted by Taylor and Francis Online.
Portland cement stone samples simulating solidified active waste were 60Co-gamma-irradiated with doses up to 108 rad. The radiolytically produced gases were determined using a gas chromatographic technique. Various additives chemically comparable to actual low- and intermediate-level wastes were incorporated in the cement mixtures. Also the influence of the presence of oxygen during the irradiation was investigated. In no case could or NOx (from the decomposition of nitrate) be detected. In nitrate-free samples, only H2 is produced. The H2 yield ranges between 3 and 8 ml of H2 per kilogram of cement stone and per megarad radiation applied. It depends on the water content and the aging time of the samples; an influence of the concrete fluidizer content was not observed. The presence of nitrate in the samples gives rise to the production of O2 besides H2 and an overall decrease of the gas yield.