REATTORI DI IV GENERAZIONE E SICUREZZA NUCLEARE
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REATTORI DI IV GENERAZIONE E SICUREZZA NUCLEARE
COLLABORAZIONE INTERNAZIONALE PER IL NUCLEARE DI IV GENERAZIONE
Xxxxxxx Xxxxxxxxx (xxxxxxx.xxxxxxxxx@xxxx.xx)
Accordo di Programma MiSE-XXXX 0000-0000 – Roma, ENEA Sede Legale, 11 settembre 2015
Contesto Europeo
SNETP
• maintaining the safety and competitiveness of today's technologies (NUGENIA)
• developing a new generation of more sustainable reactor technologies (ESNII)
• developing new applications for nuclear power (NC2I)
ESNII
• addressing the need for demonstration of Generation IV Fast Neutron Reactor technologies, together with supporting research infrastructures, fuel facilities and R&D
SRIA
• provides decision-makers and the scientific community at large with research, development and demonstration roadmaps to achieve the short (2015), medium (2020) and long-term (2040-2050) goals of the SET Plan
SNETP – Sustainable Nuclear Energy Technology Platform ESNII – European Sustainable Nuclear Industrial Initiative SRIA – Strategic Research Initiative Agenda
Contesto Europeo
“STRATEGIC RESEARCH INITIATIVE AGENDA” (SRIA)
“With respect to the 2010 technologies evaluation The
Lead Fast Reactor technology has significantly extended its technological base and can be considered as the shorter- term alternative technology, whereas the Gas Fast reactor technology has to be considered as a longer-term alternative option.”
Contesto Internazionale
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▪ Safety and Reliability
▪ Sustainability
▪ Economics
▪ Proliferation resistance
Viability
Basic concepts, technologies and processes are tested under relevant conditions, with all potential technical show-stoppers identified and resolved
Performance
Engineering-scale processes, phenomena and materials capabilities are verified and optimised under prototypical conditions
Demonstration
This phase involves the licensing, construction and operation of a prototype or demonstration system in partnership with industry and perhaps other countries. The detailed design will be completed and licensing of the system will be performed during this phase
Contesto Internazionale
FALCON CONSORTIUM*
P1HASE
• 18 months
• Unincorporated consortium
• In-kind contributions
• Optimize the cooperation
2PHASE
• Areas: strategic, management, governance, financial and technical
• Detailed agreement
• Manage the R&D needs
• Engineering design
• Licensing, and
• Commit the construction
* 18th December 2013 – 30th June 2015 extended till 30th June 2016
Contesto Internazionale
EXPLOITING POTENTIAL SYNERGIES IN FUNDS
Contesto Internazionale
Infrastructure for Cooperative Research to Advance up to Demonstration the Lead technology in Europe
iCRADLE
The iCRADLE proposal is meant to provide Europe with a Distributed Research Infrastructure (D-RI) for research, development and qualification (R&D&Q) of the Heavy Liquid Metal (HLM) technology for innovative nuclear reactors demonstration and, in a longer term, the safe and sustainable operation of future power plants
Contesto Internazionale
XXXXXX
XXXXXX is a Research Reactor, as part of an pan-European Distributed Research Infrastructure.
Advanced Lead Fast Reactor European Demonstrator
XXXXXX is a demonstrator, and not a prototype, dedicated to the development of the LFR technology.
XXXXXX is a 300 MWth reactor addressing the concerns on safety, economics and sustainability of nuclear energy.
Demonstration of a safer and more sustainable secure energy
Sinergie
LEADER – Lead cooled European Advanced Demonstrator Reactor
THINS – Thermal Hydraulic of Innovative Nuclear Systems
FREYA - Fast Reactor Experiments for hYbrid Applications
GETMAT – Gen IV and Transmutation Materials
MATTER – Materials Testing and Rules
SEARCH – Safe Exploitation Related Chemistry for HLM reactors
MAXSIMA – Methodology, Analysis and Experiments for the "Safety In MYRRHA Assessment"
ESNII+ - Preparing ESNII for HORIZON 2020
XXXXXX - Myrrha Research Infrastructure Support Action
MATISSE - Materials’ Innovations for a Safe and Sustainable nuclear in Europe
MYRTE - MYRRHA Research and Transmutation Endeavour
SESAME - thermal hydraulics Simulations and Experiments for the Safety Assessment of MEtal
cooled reactors
Struttura Generale
Analisi di Sicurezza
Infrastrutture ENEA
CIRCE
Separator
Separator
E
Heat xchanger
Heat Exchanger
Riser
Riser
Dead Volume
Dead Volume
Fitting Volume
Fitting Volume
FPS
FPS
Flow Meter
Flow Meter
Feeding Conduit
Feeding Conduit
CIRCE - Fuel Pin Simulator
CIRCE - Experimental Results
Xxxxxxx Xxxxxxxx
Nu-csc Sez-1 Nu-csc Sez-3 Nu 37 pin SST Nu 37 pin RSM
40
35
30
25
Nu [-]
20
15
10
5
00 500 1000 1500 2000 2500 3000 3500
Pe [-]
NACIE-UP
LIFUS5
Water tank
S3
S1
S2
Level measurment system
Vacuum pump
From S4 - LBE fill/drain line
Water injection line Discharge line
Coriolis flow meter
XXXXXX
LECOR
Grazie !