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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
Charles Erwin Cohn
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 12-17
Technical Paper | doi.org/10.13182/NSE62-A26122
Articles are hosted by Taylor and Francis Online.
The zero-power kinetic behavior of reflected reactors has been investigated using a simple model, in order to determine what modifications are necessary in the use of bare-reactor kinetics in interpreting experiments in reflected reactors, especially in regard to measurement of prompt neutron lifetime by kinetics methods. It is found that, for the usual reflected reactor, the kinetic behavior of experimental interest corresponds to that of a bare reactor with the same 1/v lifetime. The model is also satisfactory for an unusual case, i.e. the fast-thermal coupled critical done in ZPR-III, in which some deviation from bare-reactor kinetics is observed.