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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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
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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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.
J. T. Mihalczo, E. D. Blakeman, G. E. Ragan, R. C. Kryter, H. Seino, R. C. Robinson
Nuclear Technology | Volume 94 | Number 3 | June 1991 | Pages 336-360
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A15813
Articles are hosted by Taylor and Francis Online.
A series of subcritical experiments in unreflected annular geometry was performed with an aqueous Pu-U nitrate containing 173 and 262 g/ℓ of plutonium and uranium, respectively. The plutonium contained 91.1 wt% 239Pu, while the depleted uranium contained 0.57 wt% 235U. In these experiments, the height of the solution in the annulus was varied from 17.8 to 84.2 cm. The annulus had an inner diameter of 25.4 cm, an outer diameter of 53.34 cm, and a 0.08-cm-thick wall of Type 304L stainless steel. Measurements using the 252Cf-source-driven neutron noise analysis method were interpreted to obtain the subcritical neutron multiplication factors. The data accumulated in the experiment, which is the first test of this method in annular geometry, are summarized, and the analysis of these data is presented. The results and conclusions of these experiments are as follows: (a) the capability to measure the sub-criticality for a multiplying system of annular geometry to a k as low as 0.70 was demonstrated; (b) the criteria developed in previous experiments for choosing source-detector system configurations for which the data can be interpreted using a modified point kinetics were also satisfactory for this experiment; (c) the measurement times for this geometry were not significantly different from those used for cylindrical geometry and were sufficiently short to allow practical measurements; (d) the reactivities obtained from break frequency noise analysis measurements agreed with those obtained from the ratios of spectral densities within the experimental uncertainties; (e) the applicability of the method and an understanding of the theory of the measurement method for plutonium solution systems were demonstrated; and (f) the calculated neutron multiplication factors agreed with the experimental values of k to within ∼0.03.