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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
W. J. McCool, R. A. Robinson, E. W. Schrader, S. H. Weiss
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 47-54
Technical Paper | doi.org/10.13182/NSE61-A25864
Articles are hosted by Taylor and Francis Online.
The cold, clean, steel-reflected, final, SM-2 mock-up containing 36.4 kg U235 and 61 g B10 maintained criticality after a seven rod bank withdrawal of 6.974 in. and has an “excess K” (ΔKE) of 1520 cents. An infinite steel-water laminated reflector is worth approximately +85 cents over the infinite water reflected core. The measured reactivity coefficient, @ 2000 psi, ranges from –1.15 cents/°F @ 150°F to –5.20 cents/°F @ 510°F. The integral reactivity effect of raising the SM-2 core water temperature from 103 to 510°F @ 2000 psi and the water in the reflector coolant graph from 103 to 477°F @ 2000 psi is –889.7 cents. The average measured material coefficients for U235 and B10 are 0.157 cents/g and 42.54 cents/g, respectively. Without the benefit of flux suppressors the maximum to average power ratio of 7.28 occurs at the top of the fuel section of control rod C (withdrawn to 7.14 in.), and a ratio of 5.28 occurs at the bottom of stationary element 43 and symmetric elements.