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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
Russell B. Mesler, Harry G. O'Brien, Debow Freed
Nuclear Science and Engineering | Volume 12 | Number 1 | January 1962 | Pages 79-81
Technical Paper | doi.org/10.13182/NSE62-A25374
Articles are hosted by Taylor and Francis Online.
Laboratory experiments using pulsed neutron techniques are valuable for giving physical interpretation to elements of nuclear reactor theory encountered in the classroom. Three experiments were selected from those reported in the literature to illustrate different pulsed neutron measurements. In one case diffusion properties of a sample are measured by varying the geometry of the sample. In another the absorption cross section of a solute is measured by varying the sample without changing its geometry. A third experiment illustrates the use of a pulsed neutron source in reactivity measurements.