hcll test blanket module test program in itertritium permeation from pbli towards he coolant...
TRANSCRIPT
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International Workshop on Liquid Metals Breeder Blankets23-24 September 2010
CIEMAT, Madrid, Spain
HCLL Test Blanket Module
Test program in ITER
Y. Poitevin, M. Zmitko, I. Ricapito, Fusion for Energy
From the contribution of L. Bühler (KIT), C. Mistrangelo (KIT),
L. Sedano (CIEMAT), C. Moreno (CIEMAT)
and the TBM Consortium of Associates
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J.-F. Salavy
G. Aiello
A. LiPuma
M. Zmitko
Y. Poitevin
I. Ricapito
L. Bühler
C. Mistrangelo
L.V. Boccaccini (TBM-CA PL)
Forschungszentrum
Karlsruhein der Helmholtz-Gemeinschaft
F. Gabriel
G. Rampal
H. Simon
L. Sedano
C. Moreno
L. Batet
E. Mas de les VallsUPC
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Presentation Layout
• Main HCLL TBM design features
• ITER experimental programme
• Magneto-hydrodynamics related
tests
• Tritium cycle related tests
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HCLL Test Blanket Module
Manifolds
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PbLi flow design
inlet
outlet
manifolds
breeder units
V PbLi ~1 mm/s
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Adopted Strategy for the TBM
Programme Integration (IRP v2.0)
4 versions per each TBM are considered with
specific objectives as follow:
Learning/validation phase
the Electro Magnetic module (EM-TBM): H phase, H-He
phase;
the Thermal/Neutronic module (TN-TBM): D-phase;
DEMO-relevant data acquisition phase
the Neutronic/Tritium & Thermo-Mechanic module (NT/TM-
TBM): DT1 phase;
DEMO-relevant data acquisition phase (2nd 10 years)
the INTegral TBM (INT-TBM): DT2 (high duty, long pulses)
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ITER Experimental ProgrammeComplete
Tokamak Core
First
Plasma
Hydrogen/ Helium
Phase Complete
Deuterium Phase
Complete
Start Torus PumpDown
First Plasma
Plasma Restart
Plasma Development, H&CD Commissioning, Diag, Control, TBMs
Full H&CD, H-modes, ELM Mitigation
D Plasmas on W-Divertor
DT Plasmas
CFC/W Divertor Changeout
TBMs
Full Heating capability
H-mode Studies (D)Trace-T Studies
Q=10 Q=10 Long Pulse
DT Hybrid
DT Non-inductive
T-Plant Commissioning
Tritium Introduction
~10% T-throughput
TBM Programme EM-TBM TN-TBM NT/TM-TBM INT-TBM
Blanket
Divertor
NBI 1+2
Diagnostics
Diagnostics
H-mode Studies (He)
Hydrogen Commissioning
Diagnostics
ECRH + ICRF
Nuclear authorization
TBMs
Nuclear readiness
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MHDHCLL TBM test program in ITER
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A complex MHD sensitive design
Electrical
flow coupling
Flow bending +
narrow gap
3D expansions/
contractions
Buoyancy
phenomena
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Importance of MHD investigations in ITER
TBM
PbLi flow coupled phenomena:
- Corrosion
- Tritium permeation
- High Ha (B 4-5T)
- B (1/R)
- Btor + Bpol
- B (t)
Test conditions hardly
(not) attainable in another
facility
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• Gaining knowledge about complex coupled physical phenomena
occurring in a fusion reactor environment (e.g. magneto-convection,
electromagnetic coupling)
broadening and confirming available results coming from smaller
experimental facilities
• Creating a data base of benchmarks to validate the various stages of
the ongoing development of numerical MHD codes
• Verifying and quantifying effects of stray magnetic field, electrical
disturbances and real working conditions on the instrumentation
• Collecting data and operating experience for applications of HCLL
blankets in a DEMO reactor
suggesting suitable design modifications for improved performance of
a DEMO blanket
Objectives of MHD experimental campaign in ITER
Forschungszentrum
Karlsruhein der Helmholtz-Gemeinschaft
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Forced flow isothermal experiments (no plasma/no heat flux; EM-
TBM)
To Investigate separately MHD phenomena: there is no coupling to
heat transfer processes, where buoyancy may play an important role.
Data used to validate theoretical predictions of pressure drop and flow
distribution in the TBM.
Imposed heat flux in BUs (no plasma; EM-TBM): heated plates and
defined heat extraction through neighboring cooling plates
To study natural (buoyancy effects) and mixed convection. Outcomes
used to select and validate numerical models for magneto-convection.
Imposed thermal power and first wall heat flux (with plasma; NT-
TBM, IN-TBM)
To analyze coupled MHD and heat transfer phenomena under realistic
operating conditions (study of overall blanket performance)
Forschungszentrum
Karlsruhein der Helmholtz-Gemeinschaft
Main types of MHD experiments in ITER
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Applicability of sensors in fusion LM blanket environment (T
550°C, strong magnetic field B, T and B gradients, flowing PbLi,
corrosion)
Material production/selection (max T and PbLi compatibility)
Quantification of thermoelectric and magnetic field effects required
Achievable measurement accuracy due to small velocities in ITER
TBM: signals are very small (influence of electromagnetic
disturbances)
Lack of space (design integration constraints)
Need to optimize number and size of sensors, to define proper
integration of instruments in the TBM (e.g. cable
arrangement…)
MHD flows with buoyancy effects and mixed convection
Global electromagnetic coupling for complex 3D flows
Complemen--
ary numerical
studies
Forschungszentrum
Karlsruhein der Helmholtz-Gemeinschaft
Open issues for MHD campaign in ITER
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Illustration of invasiveness of MHD
instrumentation
TBM ½-scale mock-up
instrumented with potential
probes for test in KIT/MEKKA
facility)
– L. Bühler, C. Mistrangelo (FZK) et al., 2008
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Tritium cycleHCLL TBM test program in ITER
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HCLL TBM System Process Flow Diagram
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Physical process/phenomena considered in the
HCLL TBS tritium-related models • EU (e.g. CIEMAT) has developed good, but not-yet-validated, predictive
tools used for conceptual design specifications
• TRICICLO code, TMAP7-code based model components/systems
models approach
Tritium breeding in LM
Tritium diffusion in PbLi taking into account MHD aspects
Tritium permeation from PbLi towards He coolant (through EUROFER structures)
He bubbles phenomena (e.g. Nucleation, Transport, Stability, Coalescence)
Tritium diffusion and transfer into He bubbles; tritium trapping
He coolant chemistry
Tritium extraction from PbLi
Gas-Liquid contactor technology
Permeator –based technology (e.g. Tritium permeation through α-Fe, PdAg)
He chemistry for Tritium Recovery System (TRS)
Molecular Sieves Bed (MBS) phenomena
Cold trap (CT) phenomena
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Fundamental objectives for tritium cycle related tests in ITER
-
Determination of the tritium residence time in the HCLL and HCPB TBMs as
depending on operating parameters (e.g. T extraction efficiency, purge gas
chemistry)
Determination of the tritium permeation rate into the primary cooling system
(HCS) of both HCLL and HCPB-TBM as a function of the chemistry of the
He coolant
Determination of the ratio HTO/HT produced in the HCPB-TBM breeder
varying the purge gas chemistry
Determination of the TEU extraction efficiency as a function of the operating
conditions
chemistry of the stripping gas
temperature of the system
G/L ratio
These experimental objectives can be reached only if accurate tritium mass balances
can be performed. This requires a) reasonably low amount of tritium lost by parasitic
effects and b) good tritium accountancy.
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Additional objectives under assessment for qualification of component/system models
H-H phaseHH- #1 Study of permeation phenomena as function of various parameters (e.g. LM
temperature, LM flow rate, MF, hydrogen injection, HCS chemistry)
HH- #2 Testing of CPS performance (e.g. effect of flow rate, hydrogen p.p., HCS chemistry)
HH- #3 Testing of TES (TEU+TRS) performance (e.g. LM) temperature, stripping gas flow
rates, stripping gas pressures, stripping gas H2-dopping)
HH- #4 Assessment of global hydrogen (or deuterium) residence time in HCLL TBS
D-D phaseDD-#1 Initial study of tritium breeding prediction vs local concentration measurements
DD-#2 Study of D/T transfers between various TBS
(TBM HCS CPS ISS/WDS, TBM TEU TRS ISS/WDS, )
DD-#3 First tritium tracking and global tritium residence time assessment at TBS system
with uncertainties
D-T phaseDT-#1 Further study of tritium breeding and tracking prediction vs local concentration
measurements
DT-#2 Study of T transfers between various TBS
(TBMHCSCPSISS/WDS, TBMTEUTRSISS/WDS )
DT-#3 Tritium tracking and global tritium residence time assessment at TBS system
with uncertainties
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Open issues for HCLL Tritium cycle
related experimental program in ITER
Tritium sensors are the bottleneck of maximization of
Tritium experiments in ITER TBM
Intensive R&D is needed on:
– T sensor in PbLi
– T sensor in pressurized He
Understand He behaviour in PbLi and clarify the impact
of He bubbles on Tritium transport:
– Completion and detailed assessment of LIBRETTO
experiments (including PIE, benchmark modelling)
– Complementary Out-of-ITER tests (e.g. He micro/nano-
bubbles injection technological challenge)