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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Wolfgang von Heesen, Heinz Malmström, Rüdiger Detzer, Werner Loew
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 62-70
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33232
Articles are hosted by Taylor and Francis Online.
Interim storage plants for spent fuel elements, based on dry storage technology in transport casks, are planned in the Federal Republic of Germany. The casks are arranged in storage buildings. The decay heat is removed from the outer cask surfaces by natural convection of air entering the building through openings in the walls, and leaving through outlets in the roof As the differential equations describing the complex three-dimensional flow and temperature field can only be solved for simple boundary conditions, experiments were conducted using scaled-down models of the casks and the building The relevant similarity conditions have been investigated and used for design and operation of the 1:5 scale test setup. The cask models were heated electrically. Cask temperatures, air temperatures, as well as air flow and velocities, were measured It was found that the cooling conditions at the different cask positions show very small differences and that the cask surface temperatures inside the building are a maximum of 10°C higher than on a free-standing cask