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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
Harold Berger, James H. Talboy, Joseph P. Tylka
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 236-241
Technical Paper | doi.org/10.13182/NSE64-A18323
Articles are hosted by Taylor and Francis Online.
A method of studying the burnup of high-cross-section materials in nuclear reactor control rods by neutron radiography is described. The technique has been applied to the examination of the burnup pattern of a CP-5 reactor control rod and has been found to provide a detailed picture of the burnup pattern, showing a very sharp transition region. The radiographic study has been made by a comparison method in which the neutron transmission of the irradiated cadmium control material has been compared to that of normal cadmium. In the regions in which the cadmium control material has been highly depleted in Cd113, the equivalent normal cadmium thickness comparison can be made to an estimated accuracy of 0.0006 inch.
