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Division Spotlight
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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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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Document to preserve Swedish repository information across generations
The preservation of records, knowledge, and memory is recognized as an important component of nuclear waste management, preventing future generations from unnecessary interference with a waste repository and supporting future societies to make informed decisions about such sites.
Youho Lee, Thomas J. McKrell, Chao Yue, Mujid S. Kazimi
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 210-227
Technical Paper | Fuel Cycle and Management/Materials for Nuclear Systems | doi.org/10.13182/NT12-122
Articles are hosted by Taylor and Francis Online.
An experimental assessment was conducted of the silicon carbide (SiC) cladding oxidation rate in steam under conditions that are representative of loss-of-coolant accidents in light water reactors (LWRs). SiC oxidation tests were performed with monolithic alpha-phase tubular samples at atmospheric pressure for steam temperatures of 1140°C and 1500°C and a Reynolds number range of 40 to 330. Linear weight loss of SiC samples due to boundary layer controlled reaction of silica scale (SiO2 volatilization) was experimentally observed. The weight loss rate increased with increasing steam flow rate and temperature. Over the range of test conditions, SiC oxidation rates were shown to be about three orders of magnitude lower than the oxidation rates of Zircaloy-4. This underlines a weaker interplay between oxidation and mechanical property degradation in comparison with Zircaloy. SiC volatilization correlations for developing laminar flow in a vertical channel were formulated for LWR accident modeling.