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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
S. R. Bierman, E. D. Clayton
Nuclear Technology | Volume 15 | Number 1 | July 1972 | Pages 5-13
Technical Paper | Reactor | doi.org/10.13182/NT72-A31157
Articles are hosted by Taylor and Francis Online.
The results and analyses are presented from the latest series of experiments for determining the critical parameters of plutonium mixtures over the undermoderated region of the neutron energy spectrum. This latest series of experiments was conducted with PuO2-polystyrene fuel having anatomic H/Pu ratio of 49.6 and a 240Pu isotopic content of 18.53 wt%. In addition to providing basic criticality data, the experiments were designed to (a) establish the degree of correlation between the PuO2-polystyrene and the plutonium nitrate solution fueled critical experiments performed at the Hanford Critical Mass Laboratory, (b) provide data for checking previously reported differences obtained by the neutron diffusion theory code HFN and the neutron transport theory code DTF-IV in calculating critical sizes of plutonium-water systems between about 500 and 1000 g Pu/liter, and (c) substantiate that high exposure, subcritical, fixed volume, plutonium-water systems can be made critical by dilution with water. In contrast to the data previously obtained on this same PuO2 material unmoderated, the density effect of having the plutonium in the oxide form was found to have essentially no effect on the reactivity at 49.6 H/Pu. At 49.6 H/Pu, the minimum critical slab thickness was determined to be 5.22 ± 0.07 cm for 239Pu-H2O as compared to 5.34 ± 0.07 cm for 239PuO2-H2O However, the neutron poisoning effect of the 240Pu at 49.6 H/Pu was at least five times that observed for the PuO2 unmoderated. At this near-optimum concentration for maximum 240Pu effects, the percent change in spherical critical mass per percent change in 240Pu content was determined to be 12.1 for the reflected case and 10.2 for the bare case. Based on the data derived from these experiments at 49.6 H/Pu, the HFN code was found to accurately calculate the plutoniumwater systems at 521 g Pu/liter and should be used at this and lower concentrations in preference to the DTF-IV code for calculating critical parameters. As with the plutonium nitrate solutions at high concentrations, the DTF-IV neutron transport theory code calculations resulted in too small a critical size; however, the data obtained from the PuO2-polystyrene experiments correlated well with those that have been obtained from plutonium nitrate solutions. The experiments also showed that, for high exposure plutonium-water systems, a given size vessel could be just critical (Keff =1.0) at three different concentrations below about 1000 g Pu/liter. Consequently, a critically safe vessel could be made critical by dilution alone if the 240Pu content was high enough.