fusione, tecnologie e presidio nucleare sezione ingegneria sperimentale iea workshop on t/pb16li...
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Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium extraction from Pb16Li
and He: EU experience and proposals
I. Ricapito, ENEA CR Brasimone, FPN-FISING
Fusione, Tecnologie e Presidio NucleareSezione 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.
Tritium extraction from Pb-16Li
Tritium extraction from He (TRPS; CPS)
Proposals for EU TBMs T-systems
TES/TRPS
CPS
Possible developments
OUTLINE
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
GAS LIQUID CONTACTORS
V GETTERS
BUBBLE COLUMN-PERMEATOR (SiC-SiCf)
spray columns
bubble columns
packed columns
plate columns
Tritium Extraction from Pb-16Li
Different technologies have been proposed and studied in EU
Fusione, Tecnologie e Presidio NucleareSezione 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 NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium Extraction from Pb-16Li
Test n. LM flow-rate
(lh-1)
Ar flow-rate
(N lh-1)
PH2, in
(Pa)
(%)
1 80 -105 30 1300 -1400 10 -12
2 80 -105 60 1200 9 -11
3 50 - 65 60 1150 -1200 >14
800 mm height, 54 mm diameter, 673 K
Bubble columns: experimental results on Melodie loop
Results from Melodie loop on GL contactors
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium Extraction from Pb-16Li
Test n. LM flow-rate
(lh-1)
Ar flow-rate
(N lh-1)
PH2,in
(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
800 mm height, 54 mm diameter, packing area: 750 m2/m3, T:673 K
Results from Melodie loop on GL contactors
Packed columns: experimental results on Melodie loop
Fusione, Tecnologie e Presidio NucleareSezione 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 NucleareSezione 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 NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium Extraction from Pb16Li
TES: bubble column- permeator
High extraction efficiency is claimed to be achievable with a very compact system, but experimental confirmation is necessary
tritium is recovered by two channels in parallel:
- 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
Pb-16Li inlet
Pb-16Li outlet
He
He +Q2
He +Q2
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium Extraction from Pb16Li
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
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 column-permeator) in the ambit of international collaboration
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium Extraction from He purge (TRPS)
TRPS is the process downstream a GL based TES
TRPS feed stream depends on the GL contactor design specification
SG
CPS
P
ISS
TES
Q2
Pb-16Li
H2
TRPS
He+Q2+ imp. Q2
WGS
impuritiesHe Q2
HCS
to stack
to fuelling
H2O, H2
Fusione, Tecnologie e Presidio NucleareSezione 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
VPSA (Vacuum Pressure Swing Adsorption)
TSA (Thermal Swing Adsorption)
PdAg Permeator battery
Candidate Processes
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium Extraction from He purge (TRPS)
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)
Q2 to ISS
H2
He+Q2
pure He to TES
Adsorption column
V1
V6
V3
V2
V4
V5
VP
To Imp. Processing
VPSA process
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium Extraction from He purge (TRPS)
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)
TSA process
Fusione, Tecnologie e Presidio NucleareSezione 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)
Cooler
Blanket
Permeator 5
Water to WGSR
O2 recirculator
O2 addition
Blanket
to HISS
VacuumPump
VacuumPump
VacuumPump
VacuumPump
Permeator 4 Permeator 3 Permeator 2 Permeator 1
In the last reactor-permeator HT partial pressure in the shell side is virtually zero by oxygen addition
Fusione, Tecnologie e Presidio NucleareSezione 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 NucleareSezione 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 NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium Extraction from He purge (CPS)
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%
Possible Working Points
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
Tritium Extraction from He purge (CPS)
OUT
Q2O
impurities to WGDS
oxidizer (Cu2O-CuO)
700-750 K
ADSORBERS 2
He
RHE
He + Q2 + Q2O + imp.
IN
CT
H2O + H2
CPS: possible configuration for DEMO/Power Plant (possibly to be tested in ITER)
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
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
General Statements
Proposals for EU TBMs T-systems
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
TBMISS
CPS
TES TRPS
He purge gas
HCS
to SDS
TEPQ2
WDSA/VDS
Integration of TES/CPS in the ITER Fuel Cycle
Proposals for EU TBMs T-systems
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
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
In view of ITER
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
Proposals for EU TBMs T-systems
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
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
TMS
Proposals for EU TBMs T-systems
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
TES-HCPB: properties
Feed flow-rate (Nm3/h) 8
Temperature (K) 723
Pressure (Pa) 1000
HT molar fraction (vppm) 3.9
H2 molar fraction (vppm) 1070
HTO molar fraction (vppm) 0.13
H2O molar fraction (vppm) 3.9
Proposals for EU TBMs T-systems
TRS-HCLL: inlet gas properties
Feed flow-rate (Nm3/h) 0.23
Temperature (K) 673
Pressure (Pa) 1000
HT molar fraction (vppm) 21
H2 molar fraction (vppm) 1000
HTO molar fraction (vppm) -
H2O molar fraction (vppm) -
EU TBMs: gas stream to be processed by TES/TRPS
HCPB-TBM HCLL-TBM
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
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
Proposals for EU TBMs T-systems
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
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
Max tritium inventory in HTO form (Ci) 45 (31 mg) -
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
TES/TRPSProperties of the Q2O-TSA and Q2-TSA
Analytical instrumentation consists of:
- 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
range of the impurities as 1E-1÷1E2 vppm
TES-HCPB
Proposals for EU TBMs T-systems
TRPS-HCLL
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
CPS-HCPB: INLET GAS
Feed flow-rate (Nm3/h) 7.0
Temperature (K) 773
Pressure (MPa) 8
H2 partial pressure in the feed stream (Pa) 1000
H2O partial pressure in the feed stream (Pa) 30
T molar fraction, HT-HTO (vppm) 3.7e-2
Impurities (CO2, N2, CQ4, O2) 10
Proposals for EU TBMs T-systems
EU TBMs: gas stream to be processed by CPS
CPS-HCLL: INLET GAS
Feed flow-rate (Nm3/h) 42
Temperature (K) 773
Pressure (MPa) 8
H2 partial pressure in the feed stream (Pa) 1000
H2O partial pressure in the feed stream (Pa) 30
T molar fraction, HT-HTO (vppm) 3.7e-2
Impurities (CO2, N2, CQ4, O2) 10
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
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
Proposals for EU TBMs T-systems
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
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 -
CPS /2
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 1E-1÷1E2 vppm
Size: 4.5x1.8x2.8 m (LxWxH)
close to HCS compressor (TWCS vault)
HCPB-CPS_PFD CPS-HCPB_3D
Proposals for EU TBMs T-systems
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
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)
Possible developments /1
Tritium Extraction from PbLi
Fusione, Tecnologie e Presidio NucleareSezione Ingegneria Sperimentale
IEA Workshop on T/Pb16Li Idaho Falls, 11-12/06/2007
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 attractive for such applications but experiments on lab scale
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
Possible developments /2
Tritium Extraction from He