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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
Richard A. Condon, Neil C. Sher
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 327-338
Technical Paper | doi.org/10.13182/NSE62-A26239
Articles are hosted by Taylor and Francis Online.
A study was conducted to establish the suitability of the gamma attenuation method for measuring void fractions in a parallel rod array. A lucite mock-up was used to evaluate the accuracy of the method; the error was found to vary from 7 to 13% depending upon the measuring method. Data were taken on an air-water system flowing vertically upward at atmospheric pressure, and were found to agree reasonably well with similar data for rectangular channels and round tubes. The results of this study are being used to guide the execution of the 600 psia boiling water, void experiments which are part of the heat transfer development for the Pathfinder Boiling Water-Integral Superheating Reactor.