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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
John T. Mihalczo, Victor I. Neeley
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 6-11
Technical Paper | doi.org/10.13182/NSE62-A26121
Articles are hosted by Taylor and Francis Online.
The infinite medium neutron multiplication factor, k∞, of a mixture of 92.1 wt% UF4 and 7.9 wt% paraffin has been measured both in the Physical Constants Testing Reactor at the Hanford Atomic Products Operation and in critical experiments at the Oak Ridge National Laboratory. The density of the mixture is 4.5 gm/cc and the U235 enrichment of the uranium is 2.0 wt%, resulting in an H:U235 atomic ratio of 195. The values of k∞ 0.013 and 1.197 ± 0.013 and 1.197 ± 0.015, respectively. In the analysis of the critical experiments a two group model was assumed for the nonleakage probability. The neutron age to thermal was determined from buckling perturbation measurements as 43.1 ± 3.4 cm2. The critical buckling was measured to be (4344 ± 65) × 10−6 cm−2, the bare extrapolation distance 2.7 ± 0.3 cm, and the fast fission factor 1.039 ± 0.004. Within the experimental error, the values of k∞ from critical experiments at ORNL and from the PCTR at HAPO agree.