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
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
1

HCLL Breeder Blanket for DEMO
Structural material
Coolant
Breeder, Multiplier
Tritium extraction
RAFM steel (EUROFER)
Helium, 8 MPa,
300/500

C
Liquid breeder
Pb-15.7Li eutectic alloy
Slowly re-circulating PbLi
(a few mm/sec)
HCLL Test Blanket Module to be installed in ITER
Heat Flux / Neutron Wall Loads
He inlet/outlet, Pressure
He velocity in FW / SP / CP
Max. temperature in:
• First Wall (steel)
• CP (steel)
• PbLi/steel interface (corrosion)
0.5 / 2.4 MW/m
300 / 500 °C, 8 MPa
85 / 22 / 35 m/s
563 °C
537 °C
544 °C
2
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
2

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
3

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 4

– 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 5

ENEA - EURATOM
Solubility (Sieverts’ constant) vs. temperature (SOLE apparatus)
5x10 3 – 1.5x10
5 Pa
Diffusivity vs. temperature
(LEDI apparatus)
5x10 3 – 1.5x10
5 Pa
380 400 420 440 460 480 500 340 360
1E-7
1E-8
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.
1E-9
Reiter‘s data
1,60 1,55 1,50 1,45 1,40
1000/T (K
-1
)
1,35 1,30 1,25
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 6

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
- 10 3 – 10 5 Pa hydrogen loading pressure
- material of exp. chamber:
Pyrex glass and quartz
- PbLi in W container
T2
P1
F
OVEN
P2
P3
LV1 MV
BAG
V2
LV2
V3
QMS
G2
V1
T1
To compressed air
UHV1
G1
To
HgM
LNT
UHV2
Turbomolecular pump
Rotative pump
H
2
(D
2
) Supply
BAG Bayard-Alpert Gauge
F
G1
G2
Furnace
Electropneumatic gate valve
Manual gate valve
MV
P1,2
P3
QMS
HgM U-tube Hg manometer
LNT Liquid Nitrogen Trap
LV1,2 Manual leak valves
V2,3 Expansion volumes
T1,2
Manual magnetic valve
Capacitive manometers
Spinning rotor gauge
Quadrupole mass spectrometer
Pt-Resistance Thermometers
UHV Ultra high vacuum pumping units
V1 Experimental chamber
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls 7

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
8

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 m m 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.
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
Porous Alumina in
PbLi at 500 °C-800 h
9

– 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 10

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
S1
S1
– circulation tank
S3 – extraction column
– 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)
450
450
450
450
450
450
PbLi flow rate
(kg/s)
0,2
0,2
0,2
0,5
0,5
0,5
Stripping Ar flow rate (Nl/h)
10
50
100 - (150)
10
50
100 - (150)
11

NRI/IPP - CR
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
12

Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls 13

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 (Er
2
O
3
) 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 14

• Chemical stability/compatibility with the adjacent environment (Pb-Li,
He with H
2
/H
2
O 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 15

• 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 16

•
Development of Al
2
O
3
-based and Er
2
O
3
-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

-Al
2
O
3 and Er
2
O
3 coatings of 0.51µm 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 Er
2 permeation and anti-corrosion barrier,
O
3 or Al
2
O
3 with W to be used as a combined anti-
•
Development of suitable natural oxides , serving as the TPB, on EUROFER and/or
Inconel/Incoloy surfaces by optimization of H
2 and H
2
O 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 17

Hot-Dip aluminizing process (HDA)
Parameters for hot dipping: 700
°C, dipping time 30 s
Microstructure of hot dipped surface solidified Al
Fe
2
Al
5
HV 1000
Measurement of Permeability of HDAcoated tubes in H
2
-gas and Pb-17Li
700 650 600
1E-10
1E-11
550
HD T increase
HD T decrease
HD T increase 2
Ref T increase
Ref T decrease
Disk shaped sample
HD in gas phase
PRF  15
1E-12 10% Cr steel
230
1E-13 The alloyed surface layer consists of brittle Fe
2
Al
5
, covered by solidified Al
Microstructure after heat treatment
FeAl HV 320
1E-14
1,3 1,4 1,5 1,6
1000/T(1/K)
1,7 1,8
ENEA-Brasimone
FZK
 -Fe(Al)
10% Cr steel
270
240
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
Fe
2
Al
5
-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 18

• IPP Garching activity – Filtered vacuum arc device (PVD)
• Coatings deposited and tested as anti-permeation barriers:
- thin α-Al
2
O
3
- thin Er
2
O
3 coating on EUROFER coating on EUROFER
- thin sandwich coating W-Al
2
O
3
-EUROFER
EUROFER with 0.5 µm Er
2
O
3 coating (D. Levchuk, 2005)
Permeation characteristics of
Al
2
O
3 and Er
2
O
3 coatings
Permeation characteristics of
W-Al
2
O
3 sandwich coatings
Er
2
O
3
(222)
original
annealed 2 h
Fe-Cr
(110)
Er
2
O
3
(440)
Er
2
O
3
(400)
Er
2
O
3
(622)
28 32 36 40 44
2  , deg.
48 52 56 60
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
IPP-Garching
19

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
FZK
10 m m-thick layer of Hardalloy W on specimens of EUROFER 97
(galvanic technique)
28.09.2005
20 m m-thick layer of W-PVD on a specimen of EUROFER 97
120 m m-thick layer of plasma sprayed W on a specimen of EUROFER 97
29
CRPP W layer PS
PS-W-500 SEM micrograph of a corroded sample and XDS line profile .
20

1,E-09
1,E-10
ENEA - EURATOM

EUROFER reference value 5.7E-11 (Aiello et al.)
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
75/3
Reference Permeability (mol m-1 s-1 Pa-1/2)
1,E-11
1,E-12
6/3 20/3 35/3 45/3 55/3
Post Test Apparent Permeability
60/3
Oxyding Ratio (H2/H2O)
75/3 85/3 110/3
110/3
15
10
5
0
35
30
25
20
6/3 20/3 35/3 45/3 55/3 60/3 75/3 85/3 110/3
21

•
•
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 thermocouples purge tube eletrical heater dosimeter fluid lithium-lead
1st containment
EUROFER
2nd containment
(including heaters)
3rd containment
LIBRETTO rig design
T permeation before and after EUROFER oxidation; deterioration after 3 days of irradiation
600
500
400
Start of reactor operation
Eurofer temperature
0.5
0.4
0.3
300 Tritium production
LIBRETTO 4/1
Irradiated at 550 °C
200
0.2
Permeated Tritium
Bare EUROFER 100
Tritium permeation 25%
0
0 1 2 3 4 5 6 7 8 9 10
0
Time (Days)
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
0.1
Fe
2
O
3
/Cr
2
O
3 layer FOM-NRG
SEM picture of
Eurofer material oxidized for 1000 hours
500
LIBRETTO 4/2
Irradiated at 350 °C
Bare EUROFER
Tritium permeation 16%
0.5
Start of reactor operation
400
300
200
100
0
0 1 2 3
Eurofer temperature
4 5
Time (Days)
6
Tritium production
Permeated Tritium
7 8 9
0.4
0.3
0.2
0.1
10
0
22

- 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 (“Q2O-
PTSA”); 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 23

ENEA - EURATOM
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.
24

ENEA - EURATOM
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;
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
Removal of impurities by a second PTSA (“IMP-PTSA”)
25

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 26

• 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
Meeting on R&D for Tritium & Safety Issues in PbLi Breeders, 11-12 June 2007, Idaho Falls
TRICICLO: MathCad 12 routines/modules with
VisSim5.0H tool interface
CIEMAT
27

– 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 28

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 (10 3 -10 5 Pa), data and assessment still pending),
– verification of validity of the Sievert’s law at low T partial pressure 10 -2 – 10 2 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 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