13–15 Nov 2023
King Fahd Conference Center, KFUPM, Dhahran, KSA
Asia/Riyadh timezone

Development of Lead-Cooled fast reactor technologies at ENEA Brasimone Research Centre

14 Nov 2023, 15:50
20m
60/Ground-102 - Lecture Hall (Administration Building)

60/Ground-102 - Lecture Hall

Administration Building

80
Show room on map

Speaker

Daniele Martelli (ENEA, Fusion and Technology for Nuclear Safety and Security Department, Italy)

Description

In the framework of the GEN IV innovative nuclear system, the ENEA Brasimone RC is supporting
the technological development of innovative nuclear system cooled by heavy liquid metals (HLM)
and, in particular, by liquid lead.
ENEA Brasimone RC is currently involved in several HORIZON2020 project such as PATRICIA,
PASCAL, ANSELMUS and INNUMAT.
Since 2013 ENEA has been member of the Fostering Alfred CONstruction (FALCON) international
consortium in partnership with ANSALDO NUCLEARE and RATEN-ICN supporting the
advanced lead-cooled fast reactor European demonstrator (ALFRED) to fully demonstrates the LFR
technology viability.
Moreover, in 2022 ENEA and newcleo signed a framework agreement with the intention of
exchanges information and knowledge for the construction of a lead-cooled nuclear prototype
outside Italy. The main goal of this cooperation is the construction at the ENEA Brasimone site of
an electrical prototype of the Lead-cooled Fast Reactor (LFR) system, to allow studying the thermo-
dynamic, mechanical and functional performances.
That said, ENEA Brasimone RC host one of the largest European fleets of experimental facilities
aiming at investigating HLM thermal-hydraulics, coolant chemistry control, corrosion behavior for
structural materials, and material properties in HLM environment, as well as at developing
corrosion-protective coatings, components, instrumentation, and innovative systems, supported by
experiments and numerical tools.
Particular attention is paid to research activities on sever accident precursors in GEN IV lead-cooled
fast reactors such as steam generator tube rupture and core flow blockages.
Moreover, experimental data on the simulation of postulated accidents are used to support the
development and the validation of numerical tools for specific application to liquid metals.

Primary authors

Agostini Pietro Alessandro Del Nevo Camillo Sartorio Carlo Cristalli Chiara Ciantelli Daniele Martelli (ENEA, Fusion and Technology for Nuclear Safety and Security Department, Italy)

Co-authors

Dario Diamanti Francesco Lodi Giacomo Grasso Ivan di Piazza Marco Utili Mariano Tarantino Massimo Angiolini Paolo Favuzza Pierdomenico Lorusso Ranieri Marinari Sebastiano Cataldo Serena Bassini

Presentation materials

Peer reviewing

Paper