HCLL Test Blanket Module Test program in ITER

Transcription

1 International Workshop on Liquid Metals Breeder Blankets 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

2 J.-F. Salavy G. Aiello A. LiPuma F. Gabriel G. Rampal H. Simon L. Sedano C. Moreno Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft L. Bühler C. Mistrangelo L.V. Boccaccini (TBM-CA PL) UPC L. Batet E. Mas de les Valls M. Zmitko Y. Poitevin I. Ricapito

3 Presentation Layout Main HCLL TBM design features ITER experimental programme Magneto-hydrodynamics related tests Tritium cycle related tests

4 Manifolds HCLL Test Blanket Module

5 PbLi flow design outlet manifolds V PbLi ~1 mm/s inlet breeder units

6 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 (2 nd 10 years) the INTegral TBM (INT-TBM): DT2 (high duty, long pulses)

7 ITER Experimental Programme Complete Tokamak Core First Plasma Hydrogen/ Helium Phase Complete Deuterium Phase Complete TBM Programme T-Plant Commissioning First Plasma Plasma Restart Start Torus PumpDown Blanket Divertor NBI 1+2 ECRH + ICRF Diagnostics TBMs EM-TBM TN-TBM NT/TM-TBM INT-TBM Plasma Development, H&CD Commissioning, Diag, Control, TBMs Diagnostics TBMs H-mode Studies (He) Full H&CD, H-modes, ELM Mitigation Full Heating capability Hydrogen Commissioning Nuclear authorization Nuclear readiness Tritium Introduction Diagnostics ~10% T-throughput CFC/W Divertor Changeout D Plasmas on W-Divertor H-mode Studies (D) Trace-T Studies DT Plasmas Q=10 Q=10 Long Pulse DT Hybrid DT Non-inductive

8 MHD HCLL TBM test program in ITER

9 A complex MHD sensitive design Flow bending + narrow gap Electrical flow coupling Buoyancy phenomena 3D expansions/ contractions

10 Importance of MHD investigations in ITER TBM - High Ha (B 4-5T) - B (1/R) - B tor + B pol - B (t) Test conditions hardly (not) attainable in another facility PbLi flow coupled phenomena: - Corrosion - Tritium permeation

11 Objectives of MHD experimental campaign in ITER 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 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft

12 Main types of MHD experiments in ITER 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 Karlsruhe in der Helmholtz-Gemeinschaft

13 Open issues for MHD campaign in ITER 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 Karlsruhe in der Helmholtz-Gemeinschaft

14 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

15 Tritium cycle HCLL TBM test program in ITER

16 HCLL TBM System Process Flow Diagram

17 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

18 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.

19 Additional objectives under assessment for qualification of component/system models H-H phase HH- #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 H 2 -dopping) HH- #4 Assessment of global hydrogen (or deuterium) residence time in HCLL TBS D-D phase DD-#1 DD-#2 DD-#3 D-T phase Initial study of tritium breeding prediction vs local concentration measurements Study of D/T transfers between various TBS (TBM HCS CPS ISS/WDS, TBM TEU TRS ISS/WDS, ) First tritium tracking and global tritium residence time assessment at TBS system with uncertainties DT-#1 Further study of tritium breeding and tracking prediction vs local concentration measurements DT-#2 Study of T transfers between various TBS (TBM HCS CPS ISS/WDS, TBM TEU TRS ISS/WDS ) DT-#3 Tritium tracking and global tritium residence time assessment at TBS system with uncertainties

20 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/nanobubbles injection technological challenge)