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View article: Coupled STH/CFD calculations in support of the upcoming CIRCE-THETIS Experimental Campaign
Coupled STH/CFD calculations in support of the upcoming CIRCE-THETIS Experimental Campaign Open
In the challenge of sustainable energy development, Liquid Metal Fast Reactors (LMFRs) offer a promising solution, utilizing liquid metal coolant for enhanced safety and efficiency. As the world addresses climate change and energy security…
View article: A comparative analysis of detailed and reduced CFD approaches to model wire-wrapped fuel bundles for LMFBRs applications
A comparative analysis of detailed and reduced CFD approaches to model wire-wrapped fuel bundles for LMFBRs applications Open
The paper investigates the capabilities of different CFD modelling approaches in reproducing operating conditions relevant for Liquid Metal Fast Breeder Reactors technologies. The selected benchmark is the NACIE-UP facility wire-wrapped fu…
Loss-of-heat-sink transient simulation with RELAP5/Mod3.3 code for the ATHENA facility Open
ATHENA (Advanced Thermal-Hydraulic Experiment for Nuclear Applications) is a large multipurpose pool-type lead-cooled facility under construction at the Mioveni site in Romania. It has been identified by the FALCON (Fostering ALfred CONstr…
CFD Investigations on Heavy Liquid Metal Alternative Target Design for the SPS Beam Dump Facility Open
This study introduces numerical advancements in an alternative design for the Super Proton Synchrotron (SPS) Beam Dump Facility (BDF) at the European Laboratory for Particle Physics (CERN). The design envisions a high-power operation targe…
CFD Investigations on Heavy Liquid Metal Alternative Target Design for the SPS Beam Dump Facility Open
This study introduces numerical advancements in an alternative design for the SPS Beam Dump Facility (BDF) at CERN. The design envisions a high-power operation target made of flowing liquid lead. The BDF is a proposed versatile facility at…
View article: Liquid-Metal Thermal-Hydraulic Numerical Analyses in Support of the Upcoming CIRCE-THETIS Experimental Campaign
Liquid-Metal Thermal-Hydraulic Numerical Analyses in Support of the Upcoming CIRCE-THETIS Experimental Campaign Open
Liquid metal cooled reactors are among the design proposals accepted by the Generation IV International Forum for the fourth generation of nuclear power plants. During the last decade, many European Union (EU) projects started with the goa…
View article: IAEA’S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS
IAEA’S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS Open
A Coordinated Research Project on “Benchmark Analysis of FFTF Loss of Flow Without Scram Test” was launched by the International Atomic Energy Agency (IAEA) in 2018. A series of passive safety tests were conducted from 1980-1992 at the Fas…
CFD - STH Code Coupling for the Thermal Hydraulic Analysis of NACIE-UP Experimental Facility Open
GEN-IV Lead-cooled Fast Reactors are recognized as an economically competitive solution with intrinsic safe operation. ENEA is a member of the FALCON Consortium, which has the goal to construct the Advanced Lead-cooled Fast Reactor Europea…
Hydraulic Characterization of the Full Scale Mock-Up of the DEMO Divertor Outer Vertical Target Open
In the frame of the pre-conceptual design activities of the DEMO work package DIV-1 “Divertor Cassette Design and Integration” of the EUROfusion program, a mock-up of the divertor outer vertical target (OVT) was built, mainly in order to: …
View article: Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA
Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA Open
The next generation of nuclear energy systems, also known as Generation IV reactors, are being developed to meet the highest targets of safety and reliability, sustainability, economics, proliferation resistance, and physical protection, w…
CFD Optimization of the Resistivity Meter for the IFMIF-DONES Facility Open
A detailed study of lithium-related topics in the IFMIF-DONES facility is currently being promoted and supported within the EUROfusion action, paying attention to different pivotal aspects including lithium flow stability and the monitorin…
View article: Conceptual Design of the CSP Lead Demonstrator SOLEAD
Conceptual Design of the CSP Lead Demonstrator SOLEAD Open
The NEXTOWER H2020 EU project investigates the possibility of using liquid lead as heat storage medium for high-temperature Thermal Energy Storage (TES) in concentrated solar power plants. To that end, within such project, a demonstration …
View article: SESAME project: advancements in liquid metal thermal hydraulics experiments and simulations
SESAME project: advancements in liquid metal thermal hydraulics experiments and simulations Open
Liquid metal cooled reactors are envisaged to play an important role in the future of nuclear energy production because of their possibility to use natural resources efficiently and to reduce the volume and lifetime of nuclear waste. Sodiu…
CFD ANALYSIS OF FLOW BLOCKAGE IN THE ALFRED FA Open
In the context of GEN-IV heavy liquid metal-cooled reactors safety studies, the flow blockage in a fuel subassembly is considered one of the main issues to be addressed and one of the most important and realistic accident for Lead Fast Rea…
Blind Simulations of NACIE-UP Experimental Tests by STH Codes Open
In the frame of the SESAME project, a benchmarking activity was proposed to validate the existing system thermal-hydraulics codes for Heavy Liquid Metal reactors. More specifically, blind simulations on three well-defined experiments were …
STH-CFD Codes Coupled Calculations Applied to HLM Loop and Pool Systems Open
This work describes the coupling methodology between a modified version of RELAP5/Mod3.3 and ANSYS Fluent CFD code developed at the University of Pisa. The described coupling procedure can be classified as “two-way,” nonoverlapping, “onlin…
CFD analyses of the internal blockage in the nacie-up fuel Pin Bundle simulator Open
In the context of GEN-IV heavy liquid metal-cooled reactors safety studies, the flow blockage in a fuel sub-assembly is considered one of the main issues to be addressed and one of the most important accidents for Lead Fast Reactors (LFR).…