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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Latest News
NuScale Energy Exploration Center opens at George Mason University
NuScale Power Corporation has opened another Energy Exploration (E2) Center—this one at George Mason University in Arlington, Va. Just last month, a NuScale E2 Center opened at South Carolina State University in Orangeburg, S.C. The newest E2 at George Mason is the company’s 11th center.
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.