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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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A new ANSI/ANS standard for liquid metal fire protection published
ANSI/ANS-54.8-2025, Liquid Metal Fire Protection in LMR Plants, received approval from the American National Standards Institute on September 2 and is now available for purchase.
The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title. The Advanced Reactor Codes and Standards Collaborative (ARCSC) identified the need for a current version of the standard via an industry survey.
Typical liquid metal reactor designs use liquid sodium as the coolant for both the primary and intermediate heat-transport systems. In addition, liquid sodium and NaK (a mixture of sodium and potassium that is liquid at room temperature) are often used in auxiliary heat-removal systems. Since these liquid metals can react readily with oxygen, water, and other compounds, special precautions must be taken in the design, construction, testing, and maintenance of the sodium/NaK systems to ensure that the potential for leakage is very small.
Donald L. Keller, Lewis E. Hulbert, Bruce W. Dunnington
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 154-158
Technical Paper | doi.org/10.13182/NSE61-A28060
Articles are hosted by Taylor and Francis Online.
The complexities of the structure of dispersion fuels and of irradiation conditions makes interpretation of irradiation experiments difficult. A method is suggested for consideration of irradiation conditions independently of material variables so long as these variables are held constant. Estimates are made of the relative severity of experiments made on identical specimens under different experimental conditions. A numerical application of the analysis was made to specimens of 18-8 stainless steel with 25 and 30 w/o UO2. Approximate failure limits for both specimen compositions are obtained although both sets of data are very limited. Further experimentation is needed to more fully establish the limits of the application of the proposed model.
