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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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 G. Schweitzer
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 275-282
Technical Paper | doi.org/10.13182/NSE62-A26164
Articles are hosted by Taylor and Francis Online.
A summary is given of the work done on the thermal behavior of air-cooled graphite channels. The differences in results between this work and work done by Robinson and Taylor (5) appear to arise from the different models used. The results reported here and re-evaluation of the Robinson and Taylor work indicate that their model is not confirmed by their experiments and does not predict the limit in permissible temperatures imposed by graphite oxidation in air-cooled graphite moderated reactors.
