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Division Spotlight
Mathematics & Computation
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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 2024
Jan 2024
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Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
NEI's Korsnick delivers State of the Nuclear Energy Industry address
Nuclear Energy Institute president and CEO Maria Korsnick delivered her State of the Nuclear Energy Industry address at NEI’s 2024 Nuclear Energy Policy Forum yesterday. The forum this year is taking place May 14–16 in Washington, D.C., and serves to gather industry leaders, executives, and experts for pivotal conversations about the federal and state nuclear policy landscapes.
Korsnick updated attendees on policy priorities of the industry and gave her perspective on nuclear energy’s present and future.
Keynotes Session
Thursday, August 24, 2023|8:00–8:50AM EDT|Columbia 9/10
Session Chair:
David Luxat (SNL)
Fulvio has a Master’s Degree in Nuclear Engineering (2006) and the doctorate PhD in “Nuclear, Chemical and Safety Technology” (2010) at the University of Palermo.
Since September 2013 he has worked as a researcher at the ENEA. His technical field is the nuclear reactor thermal-hydraulics in reactor coolant systems/containment, and their coupling and the analyses of severe accident phenomena. In relation to that, he is an expert on the use of best estimate thermal-hydraulic system code (RELAP5 and TRACE) and severe accident code (ASTEC and MELCOR).
Currently he is investigating severe accident issues in PWR and BWR reactor types, the analyses of the capability of best estimate thermal-hydraulic system code to simulate the main phenomena typical of advanced light water reactor, as small modular reactor, and the thermal-hydraulic phenomena typical of fusion reactor, the analyses of the scaling issues, the analyses of the capability of severe accident code to simulate degradation phenomena, and the application of the probabilistic method to propagate input uncertainty in deterministic safety analyses.
He is involved in several international activities (e.g. EURATOM Projects, OECD/NEA/CSNI/WGAMA activities, IAEA activities, etc).
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