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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The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title.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.
D. R. Bach, S. I. Bunch, R. J. Cerbone, R. E. Slovacek
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 199-210
Technical Paper | doi.org/10.13182/NSE61-A28065
Articles are hosted by Taylor and Francis Online.
Prompt neutron decay constants have been measured for a series of polyethylene moderated subcritical assemblies. Values of keff varying between 0.20 and 1.0 were obtained by changing the physical size rather than by changing the poison concentration. The decay constants, as determined by the 1/v poison removal method, in a four-group diffusion calculation employing a group dependent buckling, agree to within 10% of the measured values. Preliminary integral type measurements of the neutron spectrum which exists in the assembly during the persistent spatial mode decay indicate that the spectrum is extremely “diffusion cooled.” A simple two-group calculation shows that the decay constant in a subcritical system is proportional to the difference of two spectra. The first is the spectrum which would exist in the assembly when excited by a time independent high energy source; the second is the spectrum existing in the assembly during the persistent mode decay of the neutron density. The conventional description of far-subcritical systems in terms of reactivity is tenuous because of the lack of well defined experiments for its determination. It is apparently more useful to characterize a far-subcritical system by its decay constant, which is directly observable.