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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
J. R. Knight
Nuclear Science and Engineering | Volume 11 | Number 3 | November 1961 | Pages 239-245
Technical Paper | doi.org/10.13182/NSE61-A25998
Articles are hosted by Taylor and Francis Online.
Due to the interest in determining the dose received by persons near a criticality accident, a method for calculating the neutron spectra and neutron dose for highly enriched uranium solutions at various hydrogen to U235 atomic ratios has been developed. This method uses the output from a code for criticality calculations, and determines the average leakage neutron energy, the neutron leakage spectrum, the first collision neutron dose, and the total neutron dose. The results of these calculations show that the average energy of the leakage neutrons and the dose per incident leakage neutron per cm2 decrease somewhat with increased hydrogen to U235 atomic ratio, but it appears that this effect is sufficiently small so that an exact knowledge of the uranium concentration would not be necessary to obtain reasonable dose estimates. The effect of neutron scattering on the neutron spectra and doses is not evaluated. No attempt has been made to describe actual dose determination methods, since these have been adequately described elsewhere.