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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
S. Zia Rouhani
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 414-419
Technical Paper | doi.org/10.13182/NSE62-A26250
Articles are hosted by Taylor and Francis Online.
It is proposed to use the (γ, n) reaction for the measurement of the integrated void volume fraction in two phase flow of D2O inside a duct. This method is applicable to different channel geometries, and it is shown to be insensitive to the pattern of void distribution over the cross-sectional area of the channel. The method has been tested on mock-ups of voids in a round duct of 6 mm inside diameter. About 40 mC Na24 was used as a source of gamma rays. The test results show that the maximum measured error in this arrangement is less than 2.5% (net void) for a range of 2.7% to 44.44% actual void volume fractions.
