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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
R. D. Baybarz
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 463-467
Technical Paper | doi.org/10.13182/NSE63-A17400
Articles are hosted by Taylor and Francis Online.
A process for separating transcurium elements from americium and curium was developed and tested in laboratory scale experiments. This separation is based on preferential extraction of the transcurium elements into 2-ethylhexylphenylphosphonic acid [2-EH(P)A] from dilute hydrochloric acid solutions. Single-stage separation factors between californium and curium are as great as 100. Extraction positions of the transplutonium elements are americium < curium ≪ berkelium < californium < einsteinium < fermium. Distribution coefficients are directly proportional to the cube of the extractant concentration in the solvent and inversely proportional to the cube of the acid concentration in the aqueous phase over the range from 1 to 4 N.
