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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
W. Rothenstein J. Helholtz
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 239-243
doi.org/10.13182/NSE62-A26212
Articles are hosted by Taylor and Francis Online.
The Dancoff correction for fuel rods surrounded by air gaps arranged in a hexagonal lattice in a moderator is calculated as a function of the rod radius measured in units of moderator mean free paths, the moderator to fuel volume ratio, and the width of the air gap relative to the radius of the rod. It is found that the Dancoff correction increases with the width of the air gap, when the other parameters are kept constant. This leads to a decrease of the mean chord length in the moderator and consequently a slight increase of the resonance escape probability, whose magnitude may be estimated from the simplest formula for the effective resonance integral.