How to recover tritium from LiPb and helium; EU experience with gas liquid contactor
Download ReportTranscript How to recover tritium from LiPb and helium; EU experience with gas liquid contactor
Tritium extraction from Pb16Li and He: EU experience and proposals I. Ricapito, ENEA CR Brasimone, FPN-FISING Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 OBJECTIVE To summarise the EU experience on tritium extraction from Pb16Li and He for DEMO and Power Plant, presenting at the same time the proposals to ITER for TBM tritium processing systems. Moreover possible fields of collaboration are indicated. OUTLINE Tritium extraction from Pb-16Li Tritium extraction from He (TRPS; CPS) Proposals for EU TBMs T-systems TES/TRPS CPS Possible developments Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from Pb-16Li Different technologies have been proposed and studied in EU spray columns GAS LIQUID CONTACTORS V GETTERS plate columns bubble columns packed columns BUBBLE COLUMN-PERMEATOR (SiC-SiCf) Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from Pb-16Li Most of the experimental activities on GL contactors were carried out on Melodie loop MELODIE LOOP: PFD Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from Pb-16Li Results from Melodie loop on GL contactors Bubble columns: experimental results on Melodie loop 800 mm height, 54 mm diameter, 673 K Test n. LM flow-rate Ar flow-rate PH2, in (%) (lh-1) (N lh-1) (Pa) 1 80 -105 30 1300 -1400 10 -12 2 80 -105 60 1200 9 -11 3 50 - 65 60 1150 -1200 >14 Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from Pb-16Li Results from Melodie loop on GL contactors Packed columns: experimental results on Melodie loop 800 mm height, 54 mm diameter, packing area: 750 m2/m3, T:673 K Test n. (%) LM flow-rate Ar flow-rate PH2,in (lh-1) (N lh-1) (Pa) 10 70-90 6 1200-1350 20-22 11 30-50 6 1000-1100 29-31 12 30-50 30 975-1000 29-31 13 30-50 6 450-475 23-25 14 30-50 6 220-230 23-25 Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from Pb16Li G-L contactors, experimental results: summary disappointing results were obtained by bubble columns because of the small G-L interface area: particularly, coalescence of gas bubble, already at low gas flow-rate, was claimed to be the main reason of the low efficiency maximum extraction efficiency was nearly 0.3, achieved with packed columns (0.8 m in height) the effect of hydrogen addition to the purge gas on the extraction efficiency was not studied L/G molar ratio was not optimised Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from Pb16Li TES: V Getters V was selected because of the high Sieverts’ constant for tritium and good compatibility with Pb-16Li A deuterium gettering rate constant in the range 10-7 10-8 mol m-2 s-1 mbar-1/2 was experimentally determined, increasing with the temperature because of the increasing deuterium diffusivity in the LM boundary layer (controlling step in the mass transfer) the system is more compact than G-L contactors for a given extraction efficiency a cyclic operation is intrinsically necessary (two beds in parallel) Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from Pb16Li TES: bubble column- permeator Pb-16Li inlet He +Q2 tritium is recovered by two channels in parallel: He - a tritium flow from LM to ascending bubbles - tritium permeation through 2D- SiCf/SiC with a sweep He flow recovering permeated Q2 or by vacuum He +Q2 Pb-16Li outlet High extraction efficiency is claimed to be achievable with a very compact system, but experimental confirmation is necessary Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from Pb16Li Ongoing activities on TRIEX loop at ENEA CR Brasimone Aims: - study and optimisation of GL contactors (first phase) - study and optimisation of alternative technologies (integrated bubble columnpermeator) in the ambit of international collaboration column operative temperature: 623-723 K; internal diameter of the column: 12.8 cm; column height: 20-120 cm specific surface of the filler: 350 m2/m3 mass flow rate of Pb-16Li: G 0.2-1.0 kg/s; Segmented packed column Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from He purge (TRPS) SG H2 P TES CPS Pb-16Li Q2 HCS H2O, H2 ISS to fuelling He+Q2+ imp. Q2 TRPS He impurities Q2 WGS TRPS is the process downstream a GL based TES to stack TRPS feed stream depends on the GL contactor design specification Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from He purge (TRPS) Tritium Removal from Purge Gas: TRPS Candidate Processes VPSA (Vacuum Pressure Swing Adsorption) TSA (Thermal Swing Adsorption) PdAg Permeator battery Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from He purge (TRPS) VPSA process Adsorption column He+Q2 VP V1 V2 V5 Q2 to ISS V3 H2 V4 V6 To Imp. Processing pure He to TES Process steps a) Feed pressurisation (all valves closed except V1) b) Adsorption at 77 K and 1-2 MPa (all valves closed except V1, V3) c) Co-current blow-down (all valves closed except V2, V4) d) H2 addition (all valves closed except V6) e) Co-current evacuation (all valves closed except V2, V5) Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from He purge (TRPS) TSA process Alternative to VPSA is a cryogenic TSA process. For this application TSA is operated at 77 K in adsorption phase, while the regeneration of the adsorbent beds takes place under counter-current He stream at RT or under vacuum, depending on the bed dimensions. Recovered Q2, concentrated in the He regeneration stream, is then processed by Q2 permeators (Pd-Ag) Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from He purge (TRPS) Pd-Ag Permeators (solution proposed for DEMO) Blanket Permeator 5 Permeator 4 Permeator 3 Permeator 2 Permeator 1 Blanket Vacuum Pump O2 addition Vacuum Pump Vacuum Pump Vacuum Pump to HISS Cooler O2 recirculator Water to WGSR In the last reactor-permeator HT partial pressure in the shell side is virtually zero by oxygen addition Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from He purge (TRPS) Considerations on TRPS TSA is more technologically mature than VPSA, especially when operated at cryogenic temperature, because of the simplicity of the regeneration phase in TSA tritium inventory is higher than in VPSA: in VPSA configuration, the adsorbent beds are much more compact than in TSA Pd-Ag permeators require large surface area and pumping power because of the low differential Q2 partial pressure (driving force) Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from He purge (CPS) About CPS… CPS is the most critical tritium system in HCLL blanket (DEMO or Power Plant) because of: - large feed flow-rate to be processed: in the worst conditions (PRF=1, low LM flow-rate) it exceeds 10 % of the total coolant flow-rate, which is unacceptable - relatively small Q2 concentration in the feed stream - presence of Q2O and impurities at very low partial pressure (range of Pa) Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from He purge (CPS) Possible Working Points LM flow-rate (kg/s) 800 1600 1600 PRF 10 10 10 TES efficiency 80% 80% 60% CPS efficiency 95% 95% 90% T_perm. rate (g/d) 12.3 4.8 9.0 Average T conc. in LM (mol m-3) 2.3x10-2 1.2x10-2 1.8x10-2 CPS feed flow-rate (Nm3/h) 2.1x106 8.2x105 1.6x106 Fraction of the coolant flow-rate 2.7% 1.1% 2.1% Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Tritium Extraction from He purge (CPS) CPS: possible configuration (possibly to be tested in ITER) for DEMO/Power Plant He + Q2 + Q2O + imp. H2O + H2 IN OUT oxidizer (Cu2O-CuO) RHE 700-750 K CT He Q2O ADSORBERS Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale 2 impurities to WGDS IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems General Statements Each TBM will have a Tritium Extraction System (TES) to extract the small amount of tritium generated Each TBM will have a Coolant Purification System (CPS) for the extraction of tritium permeated into coolant Processing of tritium within the Tritium Plant could be carried out, alternatively, through: the Tokamak Exhaust Processing System with the subsequent tritium recovery by the Isotope Separation System or the Vent Detritiation System with subsequent tritium removal / recovery by Water Detritiation System and, in series, Isotope Separation System Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems Integration of TES/CPS in the ITER Fuel Cycle He purge gas TES to SDS TRPS TBM Q2 TEP ISS HCS CPS A/VDS Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale WDS IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems In view of ITER For the EU TBMs (HCLL and HCPB), the tritium extraction from He purge could be accomplished by two diferent systems for the low duty and high duty DT phase, respectively Low duty: isolated pulses, low amount of Q2 to be extracted High duty: sequence of standard pulses (back to back pulse series) or long pulses Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems TES in the low-duty DT phase (isolated standard pulses) For the low duty DT phase, a simple “Tritium Measurement System” (TMS) could be used as TES. TMS (FZK concept) is based on a Zn reducing reactor, followed by a U getter bed it has to be equipped by suitable tritium accounting system (on line or in the tritium building) has to be placed close to the TBM (port cell) requires a space approximately 2.3x1.3x1.5 m (LxWxH) for both HCPB and HCLL TBMs Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems EU TBMs: gas stream to be processed by TES/TRPS HCPB-TBM HCLL-TBM TRS-HCLL: inlet gas properties TES-HCPB: properties Feed flow-rate (Nm3/h) 8 Feed flow-rate (Nm3/h) 0.23 Temperature (K) 723 Temperature (K) 673 Pressure (Pa) 1000 Pressure (Pa) 1000 HT molar fraction (vppm) 3.9 HT molar fraction (vppm) 21 H2 molar fraction (vppm) 1070 H2 molar fraction (vppm) 1000 HTO molar fraction (vppm) 0.13 HTO molar fraction (vppm) - H2O molar fraction (vppm) 3.9 H2O molar fraction (vppm) - Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems TES/TRPS For the high duty DT phase (back to back pulse series and long pulses), different alternatives could be envisaged. One of them is here proposed which is, in principle: - able to recover Q2 with a good efficiency (90%) and in a wide range; - able to distinguish between HTO and HT generated in the breeder; - DEMO relevant A candidate process consists, essentially, of two in series TSA systems, the first one operated at RT in adsorption phase for Q2O removal and the second one at LN2 temperature for Q2 removal. In this process the main components are: - a cooler to cool down the He stream from the TBM outlet (450°C) up to RT - a TSA for Q2O removal operated at RT in adsorption phase (for HCPB-TBM) - a pre-cooler to cool down the dry He stream close to LN2 temperature - a TSA for Q2 removal operated at LN temperature in adsorption phase - a heater to bring the pure He stream to RT - a blower to circulate the He stream into HCPB-TBM Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems TES/TRPS Properties of the Q2O-TSA and Q2-TSA parameter Q2O TSA Q2 TSA Temperature in adsorption phase 298 78 Total mass flow-rate (g/s) 0.4 (8 Nm3/h) 0.4 (Nm3/h) Duration of adsorption phase (FPh)* 36 6 Temperature in regeneration phase (K) 573, He purge RT, vacuum Duration of heating + regeneration phase (h) 6 6 He flow-rate for regeneration (Nl/h) 150 - Column length (cm) 50 60 Column internal diameter (cm) 20 20 Adsorbent material (pellet 1/16”) Silica-gel Zeolite 5 A - n. 7 ionization chambers, located in different points of the circuit. Their measurement range is 1E3÷1E6 Bq/ml - n. 3 H2 detectors, with a range of 1E-3÷1E0 % in He - n. 2 hygrometers, located in the regeneration loop of Q2O-TSA; measurement range -60÷+10 °C (d.p.) -n. 1 gas-chromatograph, with a measurement Max tritium inventory in HTO form (Ci) 45 (31 mg) - range of the impurities as 1E-1÷1E2 vppm Max Q2O inventory (g) in Q2O-TSA 0.92 - Mean Q2O molar fraction in regenerating He (%) 0.12 - Max tritium inventory in HT form (Ci) - 225 (31 mg) Max Q2 inventory (g) - 4.6 Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale Analytical instrumentation consists of: IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems EU TBMs: gas stream to be processed by CPS CPS-HCLL: INLET GAS CPS-HCPB: INLET GAS 3 3 Feed flow-rate (Nm /h) 7.0 Feed flow-rate (Nm /h) 42 Temperature (K) 773 Temperature (K) 773 Pressure (MPa) 8 Pressure (MPa) 8 H2 partial pressure in the feed stream (Pa) H2O partial pressure in the feed stream (Pa) T molar fraction, HT-HTO (vppm) Impurities (CO2, N2, CQ4, O2) 1000 30 3.7e-2 10 Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale H2 partial pressure in the feed stream (Pa) H2O partial pressure in the feed stream (Pa) T molar fraction, HT-HTO (vppm) Impurities (CO2, N2, CQ4, O2) 1000 30 3.7e-2 10 IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems CPS /1 The proposed CPS for HCPB-TBM is a three stage process, derived from the DEMO conceptual design: 1) oxidation of Q2 and to Q2O and CO to CO2 by means of an oxidising reactor (Cu2O-CuO) operated at 280 °C; 2) removal of Q2O by a room temperature PTSA (Pressure Temperature Swing Adsorption); 3) removal of the impurities by a cryogenic PTSA Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Proposals for EU TBMs T-systems CPS /2 parameter Q2O-PTSA IMP-PTSA Temperature in adsorption phase 298 78 Mass flow-rate in adsorption phase (g/s) 0.35 (7.0 Nm3/h) 0.09 (1.75 Nm3/h) Pressure in adsorption phase (MPa) 8 8 Duration of adsorption phase (h) 3 3 Temperature in regeneration phase (K) 573 373 Flow-rate in regeneration phase (Nl/h) 90 50 Pressure in regeneration phase (MPa) 0.2 0.2 Duration of heating + regeneration phase (h) 3 3 Column length (cm) 110 50 Internal Column diameter (cm) 17 15 Adsorbent material (pellets, 1/16”) Silica-gel Zeolite 13X Max tritium inventory in HTO form (Ci) 1.0 (0.7 mg) - Max Q2O inventory (g) in Q2O-TSA 2.2 - Mean Q2O molar fraction in regenerating He (%) 0.12 - Analytical instrumentation consists of: - n. 4 ionization chambers, operated in the range 1E2÷1E4 Bq/ml - n. 3 hygrometers, with a measure range -80÷0 °C (d.p.) n. 1 gas-chromatograph with detectable range of impurities 1E1÷1E2 vppm Size: 4.5x1.8x2.8 m (LxWxH) close to HCS compressor (TWCS vault) Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Possible developments /1 Tritium Extraction from PbLi Although many experiments were done in the past years on Melodie loop at CEA, experimental and modelling activities on the optimisation of tritium extraction systems from LLE need to be continued. An extensive experimental campaign is foreseen in TRIEX loop on GL contactors, particularly for packed columns, with the aim to optimise them with respect to different operating parameters: G/L, H2 content in the stripping gas, hydrodynamics. TRIEX loop is available to test other tritium extraction technologies for their study and optimisation (e.g.: permeators and coupled bubble columns/permeator) Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007 Possible developments /2 Tritium Extraction from He Technologies of tritium extraction from He have been identified for both tritium extraction from the purge gas (TRPS) and coolant purification systems (CPS) but no related experimental campaigns have been carried out so far. Adsorption technologies are potentially applications but experiments on lab scale attractive for such adsorption multicomponent equilibria on different microporous materials under relevant pressure, temperature and gas composition; adsorption kinetics and on pilot plants appear necessary taking into account the demanding performance and the very unusual feed stream properties. Modelling of the system is the next step activity, useful also to refine the sizing of TES/TRPS and CPS for ITER Fusione, Tecnologie e Presidio Nucleare Sezione Ingegneria Sperimentale IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007