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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Arántzazu Cuadra, José-Luis Gago, Francesc Reventós
Nuclear Technology | Volume 146 | Number 1 | April 2004 | Pages 41-48
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3485
Articles are hosted by Taylor and Francis Online.
Culminating in the participation of the Universitat Politècnica de Catalunya in the Organization for Economic Cooperation and Development-Committee on the Safety of Nuclear Installations/Nuclear Science Committee pressurized water reactor (PWR) main-steam-line-break (MSLB) benchmark, we present the analysis with RELAP/PARCS of a double-ended MSLB assumed to occur in the Ascó nuclear power plant (NPP). This Spanish NPP, a two-unit 1000-MW(electric) PWR plant of Westinghouse design, has been in normal operation since 1983. The utility uses the RELAP model developed by its analysts to study transients that occurred (or postulated), following its own procedures, giving response to operation-related issues, as well as serving licensing and training purposes. The model is well validated. The present study tests the RELAP/PARCS model of the Asco NPP and, in particular, tests the coupling between the neutronics and the thermal hydraulics; its focus is not licensing or validation.