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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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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.
Eduardo V. Depiante, John E. Meyer
Nuclear Science and Engineering | Volume 104 | Number 2 | February 1990 | Pages 169-182
Technical Paper | doi.org/10.13182/NSE90-A23713
Articles are hosted by Taylor and Francis Online.
The analysis of transients in nuclear power plants is a complex problem normally requiring use of simulation tools. One of these tools, known as parity simulation, exploits the concept of electrical analogs of a physical system. Electrical analogs of the components of a nuclear plant are constructed and interconnected in a highly user-oriented facility known as a parity simulator. Parity simulation originated in the study of electronic network transients and spread to neutronic and single-phase flow applications. This work focuses on the application of parity simulation to transient thermal-hydraulic two-phase flow. The development of a two-phase flow element is described. The governing mass, momentum, and energy equations along with other conditions are applied to a pipe section. The resulting model is then used to construct a circuit analog. The proposed circuit analog requires nonstandard components, the design and implementation of which is discussed. Subsequently, a formulation for a steam generator is given. Results obtained for different cases are presented. Comparison with reference numerical solutions shows general agreement in both cases.