Transcript Coordinating Meeting on R&D for (PbLi-T 2007)

Coordinating Meeting on R&D for
Tritium and Safety Issues in Lead-Lithium Breeders
(PbLi-T 2007)
11-12 June 2007, Idaho Falls, ID, USA
Recent and on-going tritium-related
activities in the EU for helium-cooled
lithium-lead blanket
M. Zmitko, G. Dell’Orco, R. Lässer, Y. Poitevin
EFDA CSU Garching
Presented by M. Zmitko
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Helium Cooled Lithium Lead (HCLL) Breeder Blanket
HCLL Breeder Blanket for DEMO
Structural material
RAFM steel (EUROFER)
Coolant
Helium, 8 MPa,
300/500C
Breeder, Multiplier
Liquid breeder
Pb-15.7Li eutectic alloy
Tritium extraction
Slowly re-circulating PbLi
(a few mm/sec)
HCLL Test Blanket Module
to be installed in ITER
Heat Flux / Neutron Wall Loads
0.5 / 2.4 MW/m2
He inlet/outlet, Pressure
300 / 500°C, 8 MPa
He velocity in FW / SP / CP
85 / 22 / 35 m/s
Max. temperature in:
• First Wall (steel)
• CP (steel)
• PbLi/steel interface (corrosion)
563 °C
537 °C
544°C
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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The liquid PbLi (breeder material) flow
The liquid PbLi is slowly
flowing (10-30
recirculations/day) for
tritium removal outside the
TBM (dedicated extraction
system in the PbLi loop)
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Presentation outline
Tritium related R&D activities in the EU
a) Tritium interaction with PbLi and transfer kinetics:
•
•
Solubility, diffusivity measurements
H isotopes partial pressure measurement in PbLi
b) Technology and components experimental testing using dedicated
test facilities:
•
•
•
TRIEX for study of tritium extraction from liquid Pb-Li
EBBTF for HCLL mock-ups and prototypes testing
LM loop for components (cold traps) testing
c) Development and qualification of anti-permeation coatings
•
•
Objectives and requirements
Current R&D program
d) Development of Tritium-related ancillary systems for HCLL TBM:
•
•
•
TES – Tritium Extraction System
TRPS – Tritium Recovery from Purge Gas
CPS – Coolant Purification System
e) Modelling of tritium transport and behaviour, tritium cycle modelling
f) Future activities
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Tritium interaction with PbLi and transfer kinetics:
Solubility, diffusivity and measurements of
hydrogen isotopes in PbLi
Associations: CIEMAT, ENEA, Pol. di Torino
Main objectives:
– Solve the discrepancies among available experimental
data on Sieverts’ constant and diffusivity values for Tritium
in Pb-Li using both desorption and adsorption
experimental techniques;
– Development and optimization of sensors for hydrogen
isotopes partial pressure measurement in PbLi:
• Optimization of design of conventional H sensors (pure iron
permeable capsule)
• Development of innovative bi-layer H sensor (porous alumina
coated by thin metallic Pd-Ag).
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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ENEA - EURATOM
H transfer kinetics in Pb-Li
Solubility (Sieverts’ constant) vs.
temperature (SOLE apparatus)
Diffusivity vs. temperature
(LEDI apparatus)
5x103 – 1.5x105 Pa
5x103T–(°C)
1.5x105 Pa
340
360
380
400
420
440
460
480
500
2 -1
D (m s )
1E-7
1E-8
1E-9
Reiter‘s data
1,60
1,55
1,50
1,45
1,40
1,35
1,30
1,25
-1
1000/T (K )
Sievert’s constant determined in SOLE (obtained with
adsorption techniques) is about 1.5 orders of
magnitude higher than Reiter’s values obtained by
desorption technique.
Diffusivity determined in LEDI is about 2 orders
of magnitude higher than Reiter’s values.
The obtained data are probably influenced by
parasitic phenomena (liquid convection and/or gas
coalescence).
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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UPV–EHU/CIEMAT
Experimental determination of Sievert’s constant and diffusivities
values for tritium in PbLi using absorption & desorption techniques
PREPARATION OF ABSORPTION – DESORPTION FACILITY
Foreseen experimental
conditions:
- 250-650°C
- 103 – 105 Pa hydrogen
loading pressure
- material of exp. chamber:
Pyrex glass and quartz
- PbLi in W container
OVEN
P1
P2
T2
F
QMS
BAG
P3
LV1
MV
G2
V3
V2
LV2
V1
T1
G1
To
compressed
air
LNT
To
HgM
Turbomolecular
pump
UHV2
Rotative pump
UHV1
H2 (D2) Supply
BAG
F
G1
G2
HgM
LNT
LV1,2
V2,3
Bayard-Alpert Gauge
Furnace
Electropneumatic gate valve
Manual gate valve
U-tube Hg manometer
Liquid Nitrogen Trap
Manual leak valves
Expansion volumes
MV
P1,2
P3
QMS
T1,2
UHV
V1
Manual magnetic valve
Capacitive manometers
Spinning rotor gauge
Quadrupole mass spectrometer
Pt-Resistance Thermometers
Ultra high vacuum pumping units
Experimental chamber
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Optimized sensors for H partial pressure
measurement in PbLi
Materials of sensor permeable capsule:
i) Nb: not suitable due to oxidation and lowering
of H permeations vs. time;
ii) Pure Fe (ARMCO 99.5%): successfully welded
and tested both in gas and PbLi phase.
Design optimization of pure iron sensors:
i) Annular geometry with reduced thickness of
wall (no He tightness);
ii) Cylindrical capsule with reduced wall
thickness; relatively high time response (2
hours).
Optimized Fe (ARMCO 99.5%) cylindrical capsule
-
Thickness of the permeable walls: 0.125 mm;
-
Manufacturing: welded with a laser technique;
-
Filler: cylinder of Al coated with Au;
-
He tightness OK.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
Experimental tests on cylindrical sensor
in gas phase at
T = 400 - 500 °C, p 10-100 mbar
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Innovative permeable bi-layer sensors for H
partial pressure measurement in PbLi
New permeable capsule has been designed to improve the dynamic performance using a thick
sensor membrane made in porous Alumina (with high hydrogen permeability and low affinity with
oxygen) coated, via magnetron sputtering technique, by 2 mm Pd or Pd-Ag layer and brazed to the
EUROFER capsule.
Porous Alumina coated by Pd/PdAg
on gas side
Porous Alumina in
PbLi at 400°C, 120 h
PbLi layer
The porous Alumina is a support while the thin metallic
Pd/PdAg coating acts as a material selective among H
isotopes.
Compatibility tests between porous Alumina and the Pb-Li
carried-out at 400-500°C up to 800 h.
Porous Alumina in
PbLi at 500°C-800 h
Neither microstructural modification nor infiltration of
molten alloy in the porous Alumina have been observed.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Technology and components experimental
testing using dedicated test facilities
Associations: ENEA, IPP-CR
Main objectives:
– TRIEX (ENEA):
– check of performances of the most promising H extraction system from Pb-Li by gas-liquid
contactors (packed columns) vs. PbLi mass flow rate and Ar stripping gas volumetric flow rate;
– change of H extractor geometry and the filler/packing columns;
– reaching of extraction efficiency > 30%;
– future tests on other extraction techniques as V-based getters and different permeators.
– EBBTF (ENEA): PbLi loop, ancillary of existing HeFus3 facility, for out-of-pile
testing of HCPB/HCLL TBM mock-ups and prototypes at ITER relevant
conditions.
– LM Loop (IPP-CR): PbLi facility to test various components of HCLL TBM
auxiliary system (e.g. a cold trap, high temperature flanges, pump) at
temperatures of 260-550°C and PbLi velocity of 5-30 mm/s.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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TRIEX loop for study of hydrogen
(tritium) extraction from liquid Pb-Li
The first experimental test campaign on TRIEX loop is in progress at
ENEA Brasimone with the objective select the most promising
hydrogen (tritium) extraction method from liquid Pb-Li (e.g.
packed columns).
ENEA - EURATOM
Main operation parameters:
Liquid metal flow-rate rate : 0.2 – 0.5 kg/s
PbLi inventory: 120 l (80 l in circulation tank)
H-extractor temperature range: 350-500°C
H2 partial pressure in Pb-Li : 200-6500 Pa
Stripping gas: Argon
Stripping gas flow-rate: 5-150 Nl/h
Extraction column filler
Test matrix for first phase of TRIEX
experiments
S2– H saturator
S3– extraction column
S1 – circulation tank
S1 – circulation tank; S2 – H saturator; S3 – extraction column;
EFT – electromagnetic flowmeter; HLM – hydrogen sensor in Pb-Li;
G – getters; H2G – hydrogen sensor in gas.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
PbLi Temp.
(°C)
PbLi flow rate
(kg/s)
Stripping Ar flow
rate (Nl/h)
450
0,2
10
450
0,2
50
450
0,2
100 - (150)
450
0,5
10
450
0,5
50
450
0,5
100 - (150)
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NRI/IPP - CR
LM loop for components (cold traps,…) testing
Development and testing of various components for HCLL TBM auxiliary system (e.g. a cold trap, high temperature
flanges, pump). Demonstration of the components feasibility (pump, flanges) and efficiency (cold trap) using
dedicated Pb-Li loop. Testing parameters: temperatures of 260-550°C and flow velocity of 5-30 mm/s.
Tank
Pump
Corrosion test section
Cold trap
Sampling
• Investigations of the cold trap purification efficiency of removing typical corrosion products (CPs) and
impurities from Pb-Li liquid metal. Cold traps: wire mesh, rings,…
• Model experiments will be performed with two eutectic compositions: (i) with higher content of CP containing
Fe, Cr, Mn, (ii) with certain content of Bi as main element of impurities. Pure metals Fe, Cr and Mn will be
added to the eutectic during the Pb-Li heat preparation. Bi will be dosed directly into the testing facility by the
special dosing equipment. CP and impurities concentrations before and after the cold trap will be analyzed
using
ICP-MS
technique.
Meeting
on R&D
for Tritium
& Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Development and qualification of Tritium
anti-permeation coatings
Associations: CEA, FZK, IPP-Garching, CRPP,
ENEA, NRG, IPP-CR
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Background
Anti-permeation coatings:
•
Tritium permeation from the Pb-Li liquid metal alloy into the He coolant and
finally into the environment is one of the most critical issue for DEMO blanket.
•
The control and reduction of tritium releases can be achieved using a suitable
tritium permeation barrier (TPB).
•
Since alumina has the capability of tritium permeation reduction, the
development of Al-based anti-permeation coatings has been selected as one
of the promising directions in the EU R&D program. Other routes are based
on development of erbium oxide (Er2O3) anti-permeation coating. Moreover, it
has been also demonstrated that natural oxides formed on the structural
material surfaces (e.g. EUROFER) can serve under certain conditions as a
TPB.
•
W-based anti-corrosion coatings, being developed to reduce or even
suppress the corrosion process and to improve structural material corrosion
resistance at critical locations of the breeder blanket, could in principle also
act as anti-permeation coating .
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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The main requirements for the anti-permeation
and anti-corrosion coatings
• Chemical stability/compatibility with the adjacent environment (Pb-Li,
He with H2/H2O and possibly other gas additions) up to the maximum
operation temperatures (approx. 550°C),
• Mechanical integrity:
– High crack resistance upon thermal cycles,
– Thermal expansion of the coating and of the substrate (EUROFER) should
be very similar,
– High irradiation resistance,
• High Permeation Reduction Factor (PRF) (valid for anti-permeation
coatings),
• Safety/environmental characteristics, e.g. low activation in fusion
spectra,
• Potential for production of coatings on complex internal or/and external
geometrical configurations,
• Potential for in-situ self-healing of any defects in the coatings that
might occur.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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R&D Programme Objectives
• The main objectives of the EU R&D programme in the direction of
the coatings is development and qualification of suitable antipermeation and anti-corrosion coatings and coating techniques in
order to be used in the HCLL breeder blanket concept.
• The coating/deposition technologies aiming at achieving required
quality, reproducibility and PRF (in the range of >10-50), and taking
into account geometry constraints of breeder blanket components.
• It is considered that such coatings & reference coating technologies
for DEMO could be tested at later stage of ITER operation (possibly
before the end of the first 10 years of ITER operation) by means of
the respective HCLL Test Blanket Module (TBM).
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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R&D program on the coatings
•
Development of Al2O3-based and Er2O3-based anti-permeation coatings:
–
–
–
–
•
Electro-chemical (galvanic) deposition of Al with subsequent heat treatment to optimize the coatings
composition and morphology,
Physical vapour deposition (PVD) process using plasma arc discharge method (possibility to
produce dense, crystalline -Al2O3 and Er2O3 coatings of 0.5-1µm in thickness),
Chemical vapour deposition (CVD) process,
Application of the pulsed electron beam technique for deposition of Al-based coating
Development of W-based anti-corrosion coatings:
–
–
–
–
Application of plasma spraying techniques, in particular Laser Assisted Atmospheric Plasma
Spraying (LAAPS) process,
Screen Printing with Laser Remelting process,
Electro-chemical (galvanic) deposition,
Physical vapour deposition (PVD) process,
•
Development of ‘sandwich’ coatings of Er2O3 or Al2O3 with W to be used as a combined antipermeation and anti-corrosion barrier,
•
Development of suitable natural oxides, serving as the TPB, on EUROFER and/or
Inconel/Incoloy surfaces by optimization of H2 and H2O addition in the He coolant,
•
Ongoing R&D on investigation of natural oxide permeation behaviour under neutron
irradiation (LIBRETTO experiments),
•
Characterization of the developed coatings in terms of morphology, metallographic
characterization, density, chemical and phase composition, adhesion to the substrate, etc.
•
Qualification of the developed coatings in terms of compatibility with flowing Pb-Li, corrosion
resistance, thermo-mechanical stability, protium/deuterium permeation characteristics,
irradiation performance, activation and decay behaviour in fusion spectra
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Development and testing of anti-permeation coating
Hot-Dip aluminizing process (HDA)
Measurement of Permeability of HDAcoated tubes in H2-gas and Pb-17Li
Parameters for hot dipping: 700°C, dipping
time 30 s
Microstructure of hot dipped surface
700
solidified Al
-1/2
-1 -1
230
The alloyed surface layer consists of
brittle Fe2Al5, covered by solidified Al
Microstructure after heat treatment
FeAl
-Fe(Al)
10% Cr steel
FZK
1E-11
PRF  15
1E-12
1E-13
1E-14
1,3
240
1,4
1,5
1,6
1,7
1,8
1000/T(1/K)
HV 320
270
550
HD T increase
HD T decrease
HD T increase 2
Ref T increase
Ref T decrease
Disk shaped sample
HD in gas phase
HV 1000
 (mol m s Pa
10% Cr steel
600
1E-10
)
Fe2Al5
650
ENEA-Brasimone
Heat treatment at 1040°C/0.5 h + 750°C/1 h
and an applied pressure of >250 bar (HIPing)
reduces porosity and transforms the brittle
Fe2Al5-phase into the more ductile phases FeAl
and -Fe(Al)
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Thin Erbia and Alumina Coatings Development
• IPP Garching activity – Filtered vacuum arc device (PVD)
• Coatings deposited and tested as anti-permeation barriers:
- thin α-Al2O3 coating on EUROFER
- thin Er2O3 coating on EUROFER
- thin sandwich coating W-Al2O3-EUROFER
EUROFER with 0.5 µm Er2O3
coating (D. Levchuk, 2005)
Permeation characteristics of
Al2O3 and Er2O3 coatings
Permeation characteristics of
W-Al2O3 sandwich coatings
original
annealed 2 h
Intensity, a.u.
Er2O3
(222)
Fe-Cr
(110)
Er2O3
(440)
Er2O3
(622)
Er2O3
(400)
28
32
36
40
44
48
52
56
60
2, deg.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
IPP-Garching
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Coatings development and testing
Development Al-based anti-permeation
coating by electro-chemical (galvanic)
technique
Development and testing of W anticorrosion coatings to improve the
corrosion resistance of EUROFER
in Pb-17Li at 550°C
Tungsten Coated Specimens
10 mm-thick layer of Hardalloy W
on specimens of EUROFER 97
(galvanic technique)
28.09.2005
FZK
CRPP
20 mm-thick layer of W-PVD
on a specimen of EUROFER 97
120 mm-thick layer of
plasma sprayed W on a
specimen of EUROFER 97
29
W layer PS
PS-W-500 SEM micrograph of a corroded sample and XDS line profile.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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ENEA - EURATOM
Testing of natural oxides on EUROFER acting as a TPB
EUROFER reference value 5.7E-11 (Aiello et al.)
1,E-09
Permeability
Apparent Permeability (A m-1 s-1 Pa-1/2)
Effect of H2/H2O ratio on
permeability and PRF;
Testing at 550 C using
deuterium
1,E-10
75/3
Reference Permeability (mol m-1 s-1 Pa-1/2)
1,E-11
Post Test Apparent Permeability
1,E-12
6/3
20/3
35/3
45/3
55/3
60/3
75/3
85/3
110/3
Oxyding Ratio (H2/H2O)
110/3
35
30
PRF
25
20
15
10
5
0
6/3
20/3
35/3
45/3
55/3
60/3
75/3
85/3
Ratio H2/H2O
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders,
11-12 June 2007, Idaho Falls
110/3
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Tritium behaviour / permeation under irradiation conditions
•
•
An irradiation campaign is ongoing in NRG Petten
to address tritium behaviour and permeation under
irradiation – LIBRETTO 4/1, 4/2 irradiations
Objectives of the LIBRETTO irradiation programme:
–
Irradiation at 350 and 550°C
–
Tritium permeation/release measurement of
bare EUROFER
–
In-situ oxidation (He saturated with water
vapour) of EUROFER outer part
–
Tritium permeation/release measurement of
oxidized EUROFER
–
Estimation of PRF caused by natural oxide
on EUROFER
fluid lithium-lead
thermocouples
1st containment
purge tube
EUROFER
2nd containment
(including heaters)
eletrical heater
3rd containment
dosimeter
LIBRETTO rig design
Fe2O3/Cr2O3 layer
FOM-NRG
SEM picture of
Eurofer material
oxidized for 1000
hours
500
Irradiated at 350°C
Bare EUROFER
Tritium permeation 16%
0.5
Start of reactor operation
Eurofer temperature
500
400
0.4
0.4
400
0.3
Tritium production
300
0.2
200
Permeated Tritium
0.1
100
Temperature ( oC)
Eurofer temperature
300
0.3
Tritium production
200
0.2
100
Tritium flow (mCi/min)
Irradiated at 550°C
Bare EUROFER
Tritium permeation 25%
0.5
Start of reactor operation
Tritium flow (mCi/min)
LIBRETTO 4/1
600
Temperature ( oC)
T permeation before and
after EUROFER oxidation;
deterioration after 3 days
of irradiation
LIBRETTO 4/2
0.1
Permeated Tritium
0
0
0
1
2
3
4
5
6
7
8
9
10
Time (Days)
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
0
0
0
1
2
3
4
5
6
7
8
9
10
Time (Days)
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Development of Tritium-related ancillary
systems for HCLL TBM
Associations: CEA, ENEA, FZK
On-going development:
- TES - Due to low tritium generation (8.79E-7 g/s) in TBM, the TES Tritium
extraction efficiency could be relaxed to around ~30%. Therefore, gas-liquid
contactors (i.e packed columns) with optimum PbLi/He stripping gas ratio (+
H2) (result from TRIEX tests) are, at present, considered;
- TRPS - Removal of impurities by an adsorbent type cartridge filter and Q2
extraction by the TSA adsorption beds;
- CPS - Tritium and impurity removal by a three step process: i) oxidation of
Q2 and CO to Q2O and CO2; ii) removal of Q2O by a first PTSA (“Q2OPTSA”); iii) removal of impurities by a second PTSA (“IMP-PTSA”).
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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ENEA - EURATOM
TRPS Tritium Recovery from Purge Gas for HCLL TBM
Tritium recovery and impurity removal by a two step process:
i)
removal of impurities by a adsorbent cartridge filters;
ii)
recovery of Q2 by a TSA adsorption beds at LN temperature
(78 K).
iii) Possible allocation in Port Cell (if space available) or in a
single glove-box in the ITER tritium plant - Size LxWxH
3.0x1.5x2.6 m3.
Recovery of Q2 by a TSA
adsorption beds at LN temp.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
Removal
of impurities by a cartridge filters
24
ENEA - EURATOM
CPS - Coolant Purification System for HCLL TBM
Tritium and impurity removal by a three step process:
i) oxidation of Q2 and CO to Q2O and CO2 at 553 K;
ii) removal of Q2O by a first PTSA (“Q2O-PTSA”) at 298/573 K;
iii) removal of impurities by a second PTSA (“IMP-PTSA”) at
78/373 K;
iv) allocation in TCWS vault - Size LxWxH 5.0x2.2x2.8 m3.
Removal of Q2O by a first
PTSA (“Q2O-PTSA”)
Oxidation of Q2/CO to Q2O
and CO2;
Removal of impurities by a
second PTSA (“IMP-PTSA”)
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Modelling of tritium transport and behaviour
Associations: CIEMAT, CEA, ENEA
Main objectives:
• Modelling of the EU breeder blankets Tritium cycles
– Development of a Computing Tool for DEMO and TBM blankets tritium
cycle (ongoing activity; COMPU task – TRICICLO code)
– Determination of ranges for tritium inventories in PbLi and He cooling
circuits of the HCLL TBM
• Modelling of Tritium permeation towards the HCS in the Breeder
Units taking into account MHD effect and T diffusivity
– Sensitivity effect of Pb-Li velocity profile in various locations of the
breeder blanket structure on T permeation (ongoing activity)
• Assessment of He bubble phenomena in Pb-Li
– He nanobubbles formation and accumulation, and the potential impact
on tritium transport behaviour (ongoing activity); He nanobubbles
formation theoretically predicted; up to approx. 25% of generated tritium
could be stripped into bubbles
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Modelling of the EU breeder blankets Tritium cycles
• The main objective is to develop a computing tool capable of providing an overall quantitative evaluation of the
tritium paths from the breeding materials into other systems, i.e. HCS, TES, CPS and the environment.
• Analyses mainly focused on the HCLL and HCPB DEMO blankets, but preliminary indications for the ITER TBM
shall be given. TRICICLO code developed.
• Determination of the environmental tritium release from the HCS loop through the SGs should result in
determination of the allowable HT partial pressure in He coolant at the inlet of the SGs.
DEMO HCLL
TRICICLO lay-out
TRICICLO: MathCad 12
routines/modules with
VisSim5.0H tool
interface
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
CIEMAT
27
Future activities – external conditions
• New organization of TBM-related activities in the EU
– Establishment of the European Joint Undertaking for ITER and
the Development of Fusion Energy named ‘Fusion for Energy’
acting as Domestic Agency for ITER (June 28, 2007); fully
operative at the end of 2007 or beginning of 2008
– TBM-related activities (TBM is considered as a Project) will be
managed and coordinated by the ‘Fusion for Energy’ that will act
as a Project Owner; it will be also responsible for an international
collaboration.
– Establishment of Consortium of Associates that will act as a
Project Contractor with the main objectives to develop, produce,
qualify, install and operate the European TBM Systems in ITER
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
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Future activities – possibilities for
collaboration (1)
Future HCLL TBM tritium & PbLi-related R&D and development activities:
– Tritium – PbLi interaction:
• Tritium solubility in PbLi, e.g.:
– experimental determination of Sievert’s constant (on-going activity (103-105 Pa), data
and assessment still pending),
– verification of validity of the Sievert’s law at low T partial pressure 10-2 – 102 Pa
• Tritium transport in PbLi, e.g.:
– experimental determination of diffusivity (on-going activity, data and assessment still
pending),
– Helium solubility in PbLi, clarification of the effect of He bubbles in liquid PbLi and
their influence on tritium transport,
– Update PbLi properties database
– Tritium permeation through structure materials:
• A lot of experimental data exists, but
• A general mass transport model allowing prediction of tritium permeation rate is
still missing (e.g. validity of the Sievert’s law for tritium-steel system at low T
p.p., effect of surface parameters for slightly oxidized steel, isotope swamping
effect,…)
– In more general: modelling and verification of tritium behaviour in TBM and
relevant ancillary systems; development and validation of a Tritium cycle
system code; determination of the most effective ways for tritium control.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
29
Future activities – possibilities for
collaboration (2)
• Future HCLL TBM tritium & PbLi-related R&D and development
activities:
– Development of instrumentation for PbLi application:
• Q2 sensor for low partial pressures
• Flow meters for low flow velocities
• Thermocouples compatible with PbLi
– Further development, testing and qualification of anti-permeation
coatings.
– Further design and experimental activities on development and
qualification of TBM-related components and ancillary systems TES
(additional TRIEX experimental campaigns), TRPS and CPS.
Development of suitable means for tritium accountancy.
– Development of technology procedure for PbLi enrichment in Li-6, nonproliferation issues, handling and transport rules.
– Neutronic analysis of Pb-Li eutectic alloy in fusion relevant neutron
spectra related to the formation of transmutation products (e.g. Bi, Po,
Hg, Tl). Set-up of the impurities limits.
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
30