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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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 2025
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Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Urenco USA feeds UF6 into new U.S. commercial enrichment cascade
Urenco USA has initiated production of enriched uranium in its newest gas centrifuge enrichment cascade—the first in a planned expansion of its Eunice, N.M., facility announced in July 2023. When the expansion is complete, early in 2027, the site will have increased its capacity by about 15 percent, adding about 700,000 separative work units (SWU) per year, the company said May 19.
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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