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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
R. C. Block, G. G. Slaughter, J. A. Harvey
Nuclear Science and Engineering | Volume 8 | Number 2 | August 1960 | Pages 112-121
Technical Paper | doi.org/10.13182/NSE60-A25786
Articles are hosted by Taylor and Francis Online.
The neutron total cross sections of U233, U235, Pu240, U234, and I129 were measured with the new ORNL fast chopper time-of-flight neutron spectrometer over an energy range from approximately O.02 to O.20 ev. The cross section data have been fitted in the energy range from approximately O.02 to O.04 ev by the least squares method to the following equation: where σT and σsc are the total and scattering cross sections, E is the neutron energy, and a and b are the coefficients of fit. From this least squares fit, the 2200 m/sec neutron total cross sections of U233, U235, Pu240, U234, and I129 were determined to be 587 ± 3, 693 ± 5, 290 ± 8, 110 ± 4, and 35 ± 4 barns, respectively. A brief description of the new ORNL fast chopper time-of-flight neutron spectrometer is included in this paper.