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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
W. D. Burch, E. D. Arnold, A. Chetham-Strode
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 438-442
Technical Paper | doi.org/10.13182/NSE63-A17395
Articles are hosted by Taylor and Francis Online.
Gram quantities of many of the transuranium elements through californium-252 will be produced for research purposes in a production program centered at Oak Ridge National Laboratory. Plutonium-242 produced in the Savannah River production reactors will be transmuted to various higher actinide isotopes in the High Flux Isotope Reactor (thermal flux—3 × 1015 neutrons/ cm2-sec) and recovered in the adjoining Transuranium Processing Plant. Calculations which optimized the production scheme are presented. The intermediate goal of the program, production of one gram of Cf252, should be accomplished by 1968.
