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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
Richard M. Bidwell
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 435-442
Technical Papers | doi.org/10.13182/NSE64-A18761
Articles are hosted by Taylor and Francis Online.
Losses of delayed-neutron precursors are estimated for liquid-metal-fueled reactor models in which the coolant is in direct contact with the flowing fuel. It is shown that as much as 90% of the precursors may be extracted by the coolant before decaying to supply neutrons. As a result, the excess reactivity corresponding to prompt critical can decrease by a factor of 10, leading to a considerable shortening of the reactor period corresponding to a given Δk. These conditions will, in actual operation at power, be alleviated by the contribution of the blanket's delayed neutrons and by the large negative temperature coefficient characteristic of liquid systems. The effects of mixing and reduced flow on delayed-neutron economy and resulting reactor period are evaluated. The benefits of reducing the flow are shown to be by far the greater, and a slower flow is recommended if enhanced control through delayed neutrons is needed at start-up.