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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
Jean-Baptiste Droin, Vincent Pascal, Paul Gauthe, Frédéric Bertrand, Gédéon Mauger (CEA)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 128-136
The present paper is dedicated to preliminary studies of the transient behavior of the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) demonstrator developed in France by CEA and its industrial partners. ASTRID is foreseen to demonstrate the progress made in Sodium Fast Reactor (SFR) technologies at an industrial scale by qualifying innovative options, some of which still remain open in the areas requiring improvements, especially safety and operability. Among the innovative options, a gas Power Conversion System (PCS) based on the Brayton thermodynamical cycle is currently considered. The main objective of such a PCS consists in physically avoiding the possibility of a sodium/water reaction with the secondary circuit.
To assess the transient behavior of such a PCS when facing incident/accident sequences, previous calculations were carried out using the CATHARE 2 thermal-hydraulics code, which considers by default the working gas as an ideal gas in its Equations Of States (EOS). However, this approximation is no longer valid for the high pressure levels of this Brayton cycle. This paper thus describes new calculations performed considering real gas EOS that are now available in CATHARE 3. The simulation of the nominal PCS working point is shown to be much more accurate than in previous CATHARE 2 calculations as the discrepancy regarding the theoretical working point is less than 1°C for the gas temperature and less than 1 % for all the components power levels (compressors, heat exchangers and turbines). The impact of this new real gas hypothesis in CATHARE 3 on an unprotected transient simulation has also been investigated on a loss of power supply case. For short time scales, the impact of such an hypothesis is demonstrated to be very low. However, an improvement of the heat extraction with the real gas option should enhance the natural convection in the primary circuit to the longer term.