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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
Karl H. Puechl
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 241-259
doi.org/10.13182/NSE61-A15607
Articles are hosted by Taylor and Francis Online.
An approach to reactor physics is developed by analysis of experimental data on ordinary water, slightly enriched uranium lattices. The developed procedure is extremely simple, and for these particular lattices, it is demonstrated that the thermal utilization factor and resonance escape probability can be calculated to satisfactory accuracy. Generalization of the procedure to all types of lattices is discussed, and a number of graphite moderated lattices are analyzed. However, detailed analysis of further experimental data is required before the generalization can be used with complete confidence. To illustrate the reasonableness of the proposed general approach and hence the desirability for continued investigation along these lines, results of criticality and core-life calculations are presented for the Calder Hall reactor and for the Yankee reactor with various enrichments.