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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
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.