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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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Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
Deep geologic repository progress—2025 Update
Editor's note: This article has was originally published in November 2023. It has been updated with new information as of June 2025.
Outside my office, there is a display case filled with rock samples from all over the world. It contains a disk of translucent, orange salt from the Waste Isolation Pilot Plant near Carlsbad, N.M.; a core of white-and-bronze gneiss from the site of the future deep geologic repository in Eurajoki, Finland; several angular chunks of fine-grained, gray claystone from the underground research laboratory at Bure, France; and a piece of coarse-grained granite from the underground research tunnel in Daejeon, South Korea.
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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