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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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. A. Ferguson, Jr., R. H. VOgt
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 397-400
Technical Paper | doi.org/10.13182/NSE62-A26248
Articles are hosted by Taylor and Francis Online.
Neutron diffraction techniques are used to measure the slow neutron spectrum of a beam from the NRL Reactor with a modified split core. The effectiveness of using one or more split fuel elements of special design to optimize the thermal flux is determined. On the basis of the measurements made it is concluded that split elements may be used to reduce the background of high-energy neutrons without depleting the thermal flux in a beam from the core.