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Nuclear for Climate: Opportunities and Challenges
Mariano TarantinoFusion and Technology for Nuclear Safety and Security Department
Fusion Technology Development.The Italian Contribution
Istituto Tecnico A. Volta, Trieste, Italy
Titolo della presentazione - Luogo e data 2Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Who we are and what we do
Overview on ENEAENEA is the Italian National Agency for NewTechnology, Energy and Sustainable EconomicDevelopment is in the field of:
ENEA Business ModelENEA’s business model:
– Develop innovative products andprocesses to commercial viability
– Provides services to private companiesand public administration
Energy
Sustainability
New Technologies
Nuclear, Renewable, Efficiency, Technology
Materials, Security, Modelling, IT
Environment, Health, Agro-Industrial
Yearly Turnover: €285Mn
Staff:~2,700 FTEs
11 Research Centers
Titolo della presentazione - Luogo e dataLo sviluppo della tecnologia della fusione: il contributo dell’Italia 3
Department of Fusion and Technology for Nuclear Safety and Security
Physics Technology Engineering Safety
Gen.IV: Design & Technology Safety Waste Management
Laser & Neutron based Systems for: Security CBRN-E Risks Environment and Medical applications
FUSION(Frascati,
Brasimone)
FISSION(Bologna,
Brasimone, Casaccia)
Security, Health, Environment
(Frascati, Casaccia)
STAKEHOLDERS
EURATOM
FUSION for ENERGY
ITER
NATIONAL & INTERNATIONAL PRIVATE AND PUBLIC INSTITUTIONS
IAEA
OECD-NEA
NATO
MINISTRIES
INDUSTRIESItalian Institute for Ionizing Radiation Measurement (Casaccia)
Titolo della presentazione - Luogo e data 4Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
ENEA delivers innovation through integrated capabilities andcooperation with industry and academia
Technology EngineeringBasicResearch
Industry Liaison
1 2 3
knowledge Know how integration
Transfer of IP, licenses, etc.
Facilitator between ind., univ. and research agencies
Joint R&D programs
4
INTEGRATION FROM CONCEPT TO EXECUTION THROUGH R&D AND PROTOTYPING
Education & Training
PhDs, Masters, Theses Joint R&D with universities
5
INTE
GR
ATIO
N B
ETW
EEN
ST
AKEH
OLD
ERS
Titolo della presentazione - Luogo e data 5Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
What is Fusion? Fusion is the process that produces energy
in the core of the Sun and other stars. Temperature in the core of the sun is ~15
million °C, pressure is 300 billionatmosphere
The fusion of light hydrogen atoms (H-H) produces a heavier element, helium Some mass has been lost and great mounts of energy have been gained
A p-p reaction cycle in the core of the sun require more than 1010
(ten billion) years
Every second 1038 p-p cycle takes place
Power density in core is ~ 300 Wm-3
Would need 107 m3 for areasonable power station!
BUT……
Titolo della presentazione - Luogo e data 6Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Which Fusion…
D-T reaction is initiated at the lowesttemperature (5 keV~58 106 K) and presents thehighest fusion cross-section @ 100 keVlighter
nuclidesheaviernuclides
Titolo della presentazione - Luogo e data 7Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Fusion & Magnetic Confinement
Typical Temperature 20 keV(150 - 200 million K)
Magnetic Field5-10 Tesla
Titolo della presentazione - Luogo e data 8Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Fusion Sustainability
Shield
Plasma
Radiation
Neutrons
CoolantFirst Wall
Blanket Vacuum vessel
MagnetsT breeding zone
FUEL
Deuterium can be extracted fromnatural water: SMOW (standardmean ocean water) contains0.016% D
Tritium must be bred internallyfrom lithium
56 kg tritium is required per GW yearof fusion power
Breeding reactions in a fusion reactor
n + 6Li → T + 4He
n + 7Li → T + 4He + n
Titolo della presentazione - Luogo e data 9Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Fusion Machine….ITER
Titolo della presentazione - Luogo e data 10Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
What will ITER do?The essential objectives of ITER are :
Produce a plasma dominated by α-particle heating; Produce 500MW of fusion power;
The world record for fusion power is held by the European tokamak JET is 16 MW, total input power 24 MW (Q=0.67);
Produce a significant fusion power factor Q≥10 500 MW of fusion power from 50 MW of input power, for long pulses (400-600 s)
Demonstrate integrated operation of technologies for a fusion power plant (i.e. Superconducting magnets, remote handling,….)
Test concepts for a tritium Breeding Blanket
Titolo della presentazione - Luogo e data 11Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
ENEA Capabilities
Experimental Physics
World Record of plasma density with Frascati Torus and Frascati Torus Upgrade (two highmagnetic field tokamaks)
FusionTheory
Among first to formalize a predictive plasma model (“first principle code”, excellence recognizedby US SciDAC)
RemoteMaintenance
New unique technology to perform optical measurements in extreme environments (i.e. highradiation, low accessibility)
High HeatFlux Technology
World record of Critical heat flux (35 MW/m2, twice as much as rocket engine power at take off)
Fusion FuelCycle
Neutronics
Breakthrough in fuel cycle technology allowing reduction in inventory of factor 3x-4x throughimproved tritium recovery and separation
Worldwide reference Lab on neutron database for: neutron shielding, tritium breeder and diagnosticdesign
World record:80 kA in a 43 mm dia cable ( sufficient for 8000 houses) Super-Conductivity
Titolo della presentazione - Luogo e data 12Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
ITER Industrial Liaison Office
ENEA is playing the role of Industrial Liaison Officer towards F4E for ITER construction, facilitating industry participation
More than 500 PMI involved Almost 1000 million euros the value of the high-tech contracts assigned to Italian Industries
ITER
Titolo della presentazione - Luogo e data 13Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
MagnetsThe ITER magnet system consists of 3 main coils
sub-systems:
18 Toroidal field coils (TFC)
A central solenoid (CS)
6 Poloidal field coils (PFC)
Industrial Partnership
Titolo della presentazione - Luogo e data 14Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Industrial PartnershipRADIAL PLATES SERIES FOR ITER TF COILS
Winding Pack
Cover Plates
Super-ConductingCable
RadialPlate
Toroidal Field Coil
The Radial Plates are the D-shaped stainless steelplates to contain the superconducting cables of ITERTF coils
Large size 13.8m x 8.7m x 110mm Very tight tolerances (Planarity < 1 mm)
High technology welds in AISI 316 LN tested at -269°C
Titolo della presentazione - Luogo e data 15Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Industrial PartnershipITER Vacuum VesselThe AMW consortium (Ansaldo – Mangiarotti – Walter Tosto) is in charge of the manufacturing of sevensectors (7 out of 9) of the Vacuum Vessel for the ITER project .
Titolo della presentazione - Luogo e data 16Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Industrial Partnership
Study, design and construction of robots for vacuum chamber tile repair/maintenance
Conceptual design of ITER In Vessel Viewing System (IVVS) and Glow Discharge Cleaning (GDC)
First Wall, Support Beam, and Vacuum Vessel Thermo-mechanical analysis (RCC-MR) for ITER
Titolo della presentazione - Luogo e data 17Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Industrial PartnershipFusion Technology Supporting Facility
Experimental plant for Tritium extraction (TRIEX)
Integrated European Lead Lithium Loop (IELLLO)
Test HAmmer in Lead LithIUM (THALLIUM)
LIFUS5 Mod3
Titolo della presentazione - Luogo e data 18
ITER Activities
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Site infrastructure, July 3rd, 2017
Titolo della presentazione - Luogo e data
Engineering Design of HCLL and HCPB TBMs
19
Completion of the Conceptual Design and the Preliminary Design of Helium Cooling System (HCS) PbLi loop Coolant Purification System (CPS) Tritium Removal System (TRS) & Tritium Extraction System
(TES)Consolidation of technical interfaces with ITERRadiation protection, releases during maintenance, accident analyses
Port Cell #16 of ITER: TRS, Pb-Li loop, HCS
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data
Design of TBM Ancillary Systems
20
This activity deals with the design on European TBM ancillaries (Cooling and Tritium systems) and theirintegration in ITER
ENEA coordinates a consortium with KIT and other partners as subcontractors (TPI, Wigner, CV-Rez,Palermo University, CREATE)
278
Helium Cooling System Layout in CVCSLo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data
Design of TBM Ancillary Systems
21
Lead Lithium Eutectic Loop Integration in ITER
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data
Tritium Extraction System Qualification
22
Investigation on TES for LLE blankets with different Technologies: GLC, PAV, VST
TREIX-II Facility
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
GLC mock-up was qualified in TRIEX-II loop in 2019 showing a tritium extraction efficiency up to 44% PAV mock-up will be qualified in 2020 in TRIEX-II loop
Titolo della presentazione - Luogo e data
Tritium laboratory
1,6 1,5 1,4 1,3 1,2 1,1
10-3
10-2
10-1
Ks (m
ol m-3 P
a-1/2 )
1000/T (K-1)
This experiment Linear fit of experimental data
_._._. Reiter data
350 400 450 500 550 600 650
Literature data (absorption technique)
T (°C)
RTs eK
12844
237,0−
⋅= [mol m-3 Pa-1/2]
PbLi Cleaned surface
Membrane sensor
Ceramic crucible
Thermocouples
HYperQuarch facility can measure Sieverts’ constantin PbLi and qualify the sensor devoted to measure Q2concentration in PbLi
New H2 permeation sensors:Test In PbLi: Tungsten crucible + upper flange cooling system
Sieverts’ constant
23Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data
HCLL in-TBM LOCA
24
The object is to experimentally investigate, supported by numerical tool (RELAP5-3D), the pressurization of LLE loop due toHCLL in-TBM LOCA .
Pressurization and the compression wave propagation into the LLE loop in case of injection of helium at 80 bar,400°C due to the rupture of a cooling plates.
Demonstrate capability of RELAP5-3D © to model single and two-phase (two fluid) wave propagation (fasttransients in liquid metal loop)
THALLIUM test section
THALLIUM DESIGN PARAMETERS
PbLi volume 150 lt
PbLi temperature 400 °C
He injection pressure 80 bar
He injection mass flow 0,1-0,4 kg/s
Design pressure 80 bar
Pressure trend in the first 150 s
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data 25
DEMO Activities
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data
Lithium Lead Eutectic Technology
26
ENEA is the coordinator of the LLE Technologies in EUROFUSION, which is organized as follow:
LLE Loop Design & Analyses (ENEA, CVR)
MHD Analyses and code validation (KIT, CIEMAT)
Corrosion (ENEA, KIT, CIEMAT, CVR)
Coolant Chemistry & Purification (ENEA, CVR)
ENEA is involved also in Tritium Technologies:
Consolidated model T transport in Breeding Unit for HCLL and WCLL
Tritium Extraction from LLE (with H)
Permeation Against Vacuum (PAV)
Vacuum Siever Tray (VST)
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data
Lithium Lead Eutectic Technology
27
LLE loops integration in Tokamak building
Cryogenicsystem/horizontal tank
NeutralbeamHeat transfer system
AREVA GmbH –Paul-Gossen-Straße 100 –91052 Erlangen, Germany
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data
Lithium Lead Eutectic Technology
28
Antipermeation/corrosion PLD coating developed by IIT/ENEA
Permeation Tests performed on PLD coating:
Hydrogen permeation through PLD coated samples at 823 K and 923 K, Hydrogen partial
pressure 100mbar.
PLD process
LLE corrosion after 1000h, 550°C
PERI II facility (ENEA)
NO corrosion
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data 29
Components and instrumentation characterization in LLE
Vortex flow meter
Permanent magnet pump
Differential pressuretransducer
Air cooler
Thermal massflow meter
Coriolis massflow meter
EconomizerA. Venturini et al., P1-125
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data
WCLL Breeding Blanket Design
30
Objective is to deliver feasible and integrated concept design of the WCLL BB for DEMO Plant at the Concept Design Review meeting
WCLL BB has to withstand severe operating conditions, ensuring (1) 3H self-sufficiency, (2) n-shielding and (3) coolant temperatures for an efficient power conversion cycle
WCLL BB features: (1) water as coolant; (2) Pb-15.7Li as breeder, n-mult and carrier; (3) Eurofer97 as structural material
Breeding blanket Establishing rationale and developing solutions
of WCLL BB 2015 design
WCLL BB 2015
Analyses of the design solutions and feedbacks
CFD
Finite Element
TMMCNP
Improvement of the design and exploiting alternative solutions
Toroidal
450
IB m
odul
e80
0 O
b m
odul
e
Back supporting structure
WCLL BB 2016
Analyses of the NEW
design solutions
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data
WCLL Safety Analysis: in-box LOCA
31
Objectives: to address the safety issues connected with PbLi/water interaction in WCLLBB in-box LOCA:• developing a reliable numerical tool for deterministic safety analysis of WCLL BB
in-box LOCA (SIMMER code for fusion application)• applying a standard code validation methodology to SIMMER code• designing and implementing a new experimental campaign in LIFUS5/Mod3
addressed to code validation
Storage tanks Water injection valves S1_B reaction vessel
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data 3232
Test Matrix• Main design parameters: 200 bar - 500 °C• Injector orifice diameters: 1 - 8 mm
• 2 Fast injection valves (opening time >250 ms)
• 4 fast pressure transducers (10 kHz)
• 5 Strain gauge (10 kHz)
• 74 type thermocouples in S1B TS (40 Hz)
• 1 level meter in the storage tank and 1 DP meter in S1B
• Dedicated Hydrogen system measurement
# D orifice[mm]
P inj[bar]
Injected H2O[g]
T H2O[°C]
T PbLi[°C]
1 4 155 50 295 330
2 4 155 50 330 330
3 4 155 50 295 450
4 4 155 100 295 330
5 4 155 150 295 330
Circumferential SG Axial SG
Radial SG
PT
74 TC 0.5 mm
LLE-water interaction: LIFUS5/Mod3 facility
Titolo della presentazione - Luogo e data
WCLL Balance Of Plant
33
Objectives
to perform power conversion studies for a Water Primary Heat Transfer System and aPower Conversion System. The reference configuration includes the integration of anEnergy Storage System (working with HITEC) to cope with the pulse operation ofDEMO
to perform R&D studies (experimental and numerical) about PbLi/water steamgenerators
Numerical tools. RELAP5/Mod3.3 versionmodified with water, HITEC and PbLi fluidproprieties
Experimental infrastructure. CIRCE facility @CR Brasimone
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data 34
Divertor Tokamak TestFacility
Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Titolo della presentazione - Luogo e data 35Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
DTT Goal
One of the main challenges in the European fusion roadmap is to design a heat andpower exhaust system able to withstand the large loads expected in the divertor ofa DEMO fusion power plant.
In parallel with the programme to optimise the operation with a conventional divertor basedon detached conditions to be tested on the ITER device, a specific project has beenlaunched to investigate alternative power exhaust solutions for DEMO, aimed at thedefinition and the design of a Divertor Tokamak Test facility.
DTT should retain the possibility to test different divertor magnetic configurations,liquid metal divertor targets, and other possible solutions for the power exhaustproblem. The DTT design proposal refers to a set of parameters selected so as to haveedge conditions as close as possible to DEMO, while remaining compatible with DEMObulk plasma performance in terms of dimensionless parameters within a set of constraintsrelated to flexibility and costs.
Titolo della presentazione - Luogo e data 36Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
CDA +EDA
Inductive
Baseline
Low capital cost and long term technologies
Construction Operation
Stellarator optimization
CFETR (CN) FNS (US)
European MST + IC
1. Plasma Operation
2. Heat exhaust
3. Materials
4. Tritium Breeding
5. Safety
6. DEMO
7. Competitive Cost
8. StellaratorBurning Plasma Stellarator
2010 2020 2030 2040 2050
DEMO decision Fusion electricity
ITER Test blanket programmeParallel Blanket Concepts
European MST +linear plasma + DTT + IC
Advanced configuration and materials
Steady state
DTT
European Roadmap
DTT Facility aiming at supporting DEMO development.
Complementary to ITER
Titolo della presentazione - Luogo e data 37Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
DTT Partnership
Titolo della presentazione - Luogo e data 38Lo sviluppo della tecnologia della fusione: il contributo dell’Italia
Status of the Project
Italian Government committed in supporting the Project
Project approved and funded by EUROFUSION
Funds available
Design and Construction started in Frascati (ENEA RC)
Licensing Ongoing
Titolo della presentazione - Luogo e data
Mariano Tarantinomariano.tarantino@enea.it
Titolo della Presentazione – Luogo e dataLo sviluppo della tecnologia della fusione: il contributo dell’Italia
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