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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
G. G. Gaul, W. L. Pearl
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 30-41
Technical Paper | doi.org/10.13182/NSE63-A17207
Articles are hosted by Taylor and Francis Online.
Type 304 stainless steel cladding material has been corrosion tested under heat transfer conditions at metal temperatures up to 1300°F in specially constructed out-of-pile superheat facilities. The hydrogen and oxygen contents of the steam have been controlled to simulate that found in boiling water reactor type systems. Good corrosion resistance and low metal release to system up to metal temperatures of 1100°F were experienced with an expected pattern of an initially high corrosion rate that decreased to a lower constant rate with time up to 4500 hr. A compositionally disturbed layer developed adjacent to the scale in the 1100°F to 1300°F metal temperature range on the heat transfer specimens. The layer continued to grow with time but had little effect on the corrosion rate within the 2500 hours of testing.