ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
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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May 2025
Latest News
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.
Frank Kedziur
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 9-22
Technical Paper | doi.org/10.13182/NSE82-A19591
Articles are hosted by Taylor and Francis Online.
Stationary two-phase flow experiments at pressures up to 13 MPa and temperatures up to 600 K have been performed in a converging nozzle. The experiment is specially designed for the assessment of two-phase computer codes used in reactor safety analysis, in particular for loss-of-coolant accident blowdown calculations. An assessment by the codes DUESE, DRIX-2D, and RELAP4/MOD6 is reported. The shape of the nozzle, the instrumentation, and the experimental program are such that models and empirical parameters of a wide range of codes can be tested and determined, respectively. Results show the influence and magnitude of models and parameter variations, the effect of the dimensionality and the difference scheme of the code, and the relevance of the models as a function of the initial conditions.