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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
D. E. Wood, K. R. Birney, E. Z. Block
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 116-125
Technical Paper | doi.org/10.13182/NSE64-A18148
Articles are hosted by Taylor and Francis Online.
Lattice parameters have been measured for natural uranium concentric tubes and solid fuel elements of 2.5 inches outside diameter in the Physical Constants Testing Reactor (PCTR). The primary quantities measured are the mass of copper required to reduce k∞ to one, copper activations throughout the lattice, and cadmium ratios for U238 capture, U235 and U238 fission, copper, gold, and lutetium. The results derived from these measurements are k∞, ε, and the effective neutron temperature for the concentric tube in a 10.5-inch graphite lattice with both water and air in the coolant channels; k∞ and for the concentric tube in an 8.375-inch lattice, water cooled only; and k∞, , and for the solid fuel in a 10.5-inch graphite lattice, water and air cooled. The effective fraction of the internal surfaces for resonance capture was determined to be 0.50. The average value of η for natural uranium in these lattices was found to be 1.30.