Sandro Paci

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Professore ordinario

University of Pisa

Italy

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About

Sandro Paci is a Professore ordinario at Università degli Studi di Pisa in Italy. His research focuses on predictive monitoring and residual useful life estimation in nuclear power plant components, as well as the thermal response of dry casks for spent nuclear fuel. He has published extensively on topics related to severe accident research, including the impact of backfill gas pressure and uncertainty analysis in nuclear safety. Paci has also contributed to significant EU projects and conferences addressing advancements in fusion safety and thermal-hydraulic phenomena.

Recent Grants

Grant: Close

SEVERE ACCIDENT RESEARCH AND KNOWLEDGE MANAGEMENT FOR LWRS (SEAKNOT)

Open Date: 2022-10-01

Close Date: 2026-09-30

Grant: Close

MUSA: Management and Uncertainties of Severe Accident

Open Date: 2019-06-01

Close Date: 2023-05-01

Grant: Close

SARNET2: Network of Excellence for a Sustainable Integration of European Research on Severe Accident Phenomenology and Management – Phase 2

Open Date: 2009-04-01

Close Date: 2013-03-01

Grant: Close

THENPHEBISP: Thematic Network for a Phebus FPT-1 International Standard Problem

Open Date: 2001-12-01

Close Date: 2003-11-01

Articles (15)

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2025

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2021

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2021

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2021

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2021

Collaborators (4)

Xue Zhou Jin

Karlsruhe Institute of Technology

GERMANY

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RICCARDO CIOLINI

Associate Professor

University of Pisa

ITALY

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Rosa Lo Frano

Professor

University of Pisa

ITALY

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Mihaela Ionescu-Bujor

Karlsruhe Institute of Technology

GERMANY

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Sandro Paci

Research Interests

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About

Recent Grants

Articles (15)

Hybrid neural network and statistical forecasting methodology for predictive monitoring and residual useful life estimation in nuclear power plant components

Major Achievements of the EC MUSA Project

The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel

Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project

On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions

Current status of MELCOR 2.2 for fusion safety analyses

ERMSAR-2022 conference “Severe accident research: Eleven years after the Fukushima accident”

Lithium-Lead/water interaction: LIFUS5/Mod3 series E tests analysed by SIMMER-III coupled with RELAP5

Overview of key thermal–hydraulic phenomena in severe accident unfolding: Current knowledge and further needs

Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel

Best-Estimate for System Codes (BeSYC): A New Software to Perform Best-Estimate Plus Uncertainty Analyses with Thermal-Hydraulic and Safety System Codes for Both Fusion and Fission Scenarios

Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code

Preliminary analysis of an aged RPV subjected to station blackout

The EC MUSA Project on Management and Uncertainty of Severe Accidents: Main Pillars and Status

Post-test analysis of Series D experiments in LIFUS5/Mod3 facility for SIMMER code validation of WCLL-BB In-box LOCA

Collaborators (4)

Xue Zhou Jin

RICCARDO CIOLINI

Rosa Lo Frano

Mihaela Ionescu-Bujor

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