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Conference Spotlight
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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
G. D. Hickman, J. A. Bistline, L. A. MacNaughton
Nuclear Science and Engineering | Volume 8 | Number 5 | November 1960 | Pages 381-392
Technical Paper | doi.org/10.13182/NSE60-A25818
Articles are hosted by Taylor and Francis Online.
A series of fifteen experiments were carried out on an 8 × 30 × 32 in. core in the Pressurized Critical Assembly at KAPL. In twelve of these experiments, 0.030-in. boron stainless steel septa bisected the 8-in. dimension. These septa contained various weight per cent B10. In the remaining three experiments, there were no boron-stainless steel septa in the core. The eigenvalues and neutron density distributions were compared with values which were calculated using Deutsch cross sections and “Thin Region Theory.” The eigenvalues which were calculated were within one per cent of the experimental values, with a spread of approximately one per cent. For all the cores, the calculated eigenvalues were lower than the experimental values. Analyses of the neutron density distributions showed the calculated results in fairly good agreement with the experimental results. In all cases, this agreement was as good for the cores which contained the boron septa as for the ones which did not. It therefore appears that the boron has been well represented by “Thin Region Theory,” and that the main discrepancies between calculated and experimental values are due to the inadequacies of adapting the Deutsch scheme to these cores.