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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
L. M. Howe, R. E. Jervis, T. A. Eastwood
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 185-189
Technical Paper | doi.org/10.13182/NSE12-2-185
Articles are hosted by Taylor and Francis Online.
Aluminum-gold alloy wire of very uniform cross section and composition has been made for the preparation of neutron flux monitors. Because the wire is uniform, a device to cut it into pieces of equal length can be used for the rapid preparation of flux monitors and the need to weigh individual monitors can thus be avoided. Homogeneity of composition was achieved mainly by rolling and annealing, and the effectiveness of each step was assessed by neutron-activation analysis. The gold content of the final product (wire 0.018 in. diameter) was also determined by activation analysis and was found to be 0.0985 ± 0.0020 atom %. Thermal-neutron self-shielding in this wire is negligible and cadmium ratio experiments show that resonance-neutron self-shielding amounts to about 2.5%.