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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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.
Manuel G. Vigil, Amado A. Trujillo, H. Richard Yoshimura
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 514-520
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33176
Articles are hosted by Taylor and Francis Online.
Full-scale experimental measurements on the thermal effects of torch fires on a large spent nuclear fuel shipping cask have been obtained. The measured temperature data in the various materials of the multilayered cask are unique, since no torch tests have been previously performed on a cask. These data were obtained during a series of four torch tests that simulate a situation in which the relief valve of a liquefied gas tank railcar has been opened and the contents are vented and ignited so that the resultant torch impinges on the cask. An existing spent fuel cask was modified, and temperature data were obtained in the various materials of the multilayered cask using stainless-steel sheathed thermocouples. Results of these tests indicated that the surface temperatures for the cask with a voided neutron shield were about twice as high as those for a cask having a neutron shield filled with water. The wood in the impact limiter effectively prevented thermal penetration, limiting the temperature rise of the inner cavity to only 13°C in test 4. The maximum temperature rise of the inner cavity surface, which occurred in test 3 with the neutron shield voided, was 80°C. These thermal data will be used to refine a transient thermal analytical model, which can then be utilized to predict the thermal response of other nuclear material shipping system designs subjected to torch fire environments.