1. JET EP2 enhancement
program
“Keep in touch”
Cadarache 26-27 Feb 2008
Presented by D. Fraboulet

2. Rationale for ITER wall materials choice
ITER
Tungsten
• Low erosion
• high melting T
• Negligible T retention
Optimise lifetime & T- retention
But high Z & melting
Beryllium first wall
• low Z
• Oxygen getter
Optimise plasma performance
But large erosion & melting
Graphite CFC
• Lowish Z
• No melting in transients
• Superior heat shock behaviour
Optimise heat flux resistance
But large erosion & T retention
W
CFC
JET

3. The JET programme in support of ITER
• JET Scientific objectives
– Experimentation with ITER-like wall and divertor materials
– Development of fully integrated ITER-relevant plasma
scenarios
– Ultimately: integrated experimentation in Deuterium-Tritium
• JET On-going enhancements
– ITER-like Beryllium wall and Tungsten divertor
– Upgrade of auxiliary heating systems
(NBI from 20 to 40MW, 10 to 20s)
– High frequency pellet injection system for ELM control
(already installed)
– Plasma control upgrade
– Diagnostics (18 diagnostics)

4. Feb 2008 Status of EP2 JET EFDA Art.7 contracts
• Contracts (total / final delivery / running)
• ILW (19 / 3 / 16 running )
• NBE (9 / 1 / 8 running )
• ERFA (1 / running)
• HFPI (4 / 3 / 1 )
• Diagnostics (27/ 11 / 16 running )
– Divertor IR camera (1 / running)
– Fast visible camera (1 / running)
– Spectroscopy upgrade (12 / 3 / 9 )
– Lithium beam upgrade (1 / final delivery)
– Gamma ray spectroscopy (5 / 2 / 3 )
– ECE extension (3 / 3 / 0 )
– Edge Lidar upgrade (3 / 3 / 0 )
– Compact neutron spectrometer (1 / running)
• 60 contracts:
19 reached final delivery, 41 running, all signed.
ILW:
Art 7 (34ME)
JOC
TA(4.5ME)

5. Timeline to completion of installation
Plasma restart Before Nov 2010
EP2-Shut Down start
Somewhere mid 2009
Issues
-Contracts may run late…
-Complex synchronisation of actions
-RH versus Manual phase and ALARA
- …

6. Upper
Dump
Plate
Inner Wall
Guard
Limiters
Mushrooms
Saddle coil
protection
Saddle Coil
Protections
Poloidal
Limiters
LH + ICRH
Protection
Beryllium
Normal NBI IW
Cladding
Magnetic
covers
B&C
tiles
W-coated
CFC
Divertor
Re-ionisation
Protections
Restraint Ring
Protections
Normal NBI Inner
Wall GL’s
Inner Wall
Cladding
Inconel+8µm
BeBulk W
Bulk W
JET-ILW : Straightforward principles

7. JET-ILW Engineering : A complex reality
Inner Wall lay out
Be coated
Inconel
Normal Bank
Shinethrough
area
(recessed)
W-coated
CFC
(10µm)
W-coated
CFC transition
tile
W-coated
CFC wings
for
Tangential
Bank
Be tiles
+3cm
Inner Wall - NBI shinethrough areas
Related Contracts (Art 7, 25 ME)
-Berillium Brush Wellman (6.3)
Index, LA Gauge, Atmostat (8.7)
-CFC Dunlop (2.8)
Carbone Loraine (0.7)
-Inconel CTi (2.5), machining ETG (2.7)
-Bolt & Nuts (0.25), Jigs Morson(0.23)
-…

8. Bulk W concept developed under leadership of FZ Juelich
minimises EM forces and optimise mechanical stability
-6 mm W lamellae, poloidal stacks, toroidally isolated
R&D on bulk W concept
Option 1
20 MJ
Toroidally isolated
T Hirai O3A-F-359; Ph. Mertens P2-F-470
S. Sadakov P2-F467; E. Borovkov P2-F-
31
Related Contracts :
-MG Sanders Art 7 (5ME, on time)
-TA with FzJ & SCK (580kE)
-Project Scientist (140kE)
Potential Issues:
- Mascot 100kg upgrade necessary
- Design for W chain like fixing
- Back up W coated CFC still running

9. W coatings
C
1
3
4 6
7
8
HFG
C
55
a
B
2D CFC : not an easy material to cover…
Related Contracts (Art 7, ME) (TA, ME)
-W Coatings : Plansee (0.6), TA MeC Ro
-Be coatings TA MeC Ro
-Gladis (IPP) Judith (FzJ) JOC & TAs
(ILB+ILC+ILT+ILW = 2.1)
Major Issue :
- Next Project Board 6-7 March :
- Final thick coating choice (200µm=>14µm?)
Bulk W
Or
CFC+Thick W
CFC+Thick W
CFC
+
Thick W

10. Flanged Joint
Trolley
Main Boom Section
Slew
Ring
Flan
Vertical Traverse Section
Task
Module
ILW: two Remote Handling booms acting in synergy
Octant 5 Octant 1
Related Contracts :
-Cybernetix/Astriane Art 7 (900k)
-DML JOC Contract (1ME)
-Mascot Motors (260k, done)
Issues :
-Ext. Companies very late & Overcost
issues. Welding quality too low.
-Relationship with OTL
-Contractual status of UKAEA
assimilated staff

11. Top (W24) Tile
Carrier Tool
Bottom (W1) Tile
Carrier Tool
W4 Tile Carrier Tool
Torque Wrenc
Remote Handling tooling
Divertor tile-carrier tooling
Related contracts :
-Internal Design for the most criticals
-Small JOC contracts for design and manufacture
(1.3 ME or more in total)
Issue :
- design very late
- external JOC tendering difficult
Total new
RH tools
~ 138
W5 Tile Carrier Tool

12. ILW Embedded diagnostics
Related contracts :
-Centronics (400k)
-LCN (950k)
-Lemo (24k)
-RMP (720k)
-Striped tiles TA MeC
-EDP TA (750k)
Issue :
-design very late.
-Scale down is still an eventuality
(Thermocouples,Langmuir probes)

13. Logistics and Shut Down preparation
Written
Safe
System
of Work
- Be Inspection Facility
- Iso Containers
Related contracts:
JOC
Issues:
-Be machining on site ?
-RH v.s. Manual Entry ?
-Necessity of WSSW
-Additionnal engineering
ressources in RH
-(LIST? Finland?)

14. Projects Daily issues
• Contracts preparation (tendering, signature, etc…)
• Manage Contract follow up (more complex, more
expensive, late,…)
• Ensure respect of planning and follow project
organisation (Who? What? When?)
• Monitor Internal JET critical issues
– Design process (DO critical, TCDi signatures)
– Shutdown preparation (RH critical)
• Risk Management.
« Quality »
Delay0 (on time)
One contract
Many intertwined industrial contracts

15. Conclusion and Coments for JET EP2
• Strong « non technic » prevaled at the start of the projects => « Late
mode » is the norm.
• Recovery is rather good but risks are still there, on delays and on
technical issues. As Guy Matthews would Say: « it is astounding
that we have not encountered more problems up to now »
• EP2 Integration now under way: Compatibility of NBE, Diags, ILW
and acceptable plannings !
• « Cultural differences » are also an important reality.
• CSU? A harsh but fantastic experience.

17. NBE
Spare slides

18. EP2: Neutral beam Upgrade
Injected energy (MJ)
Injectedbeampower(MW)
0 200 400 600 800
0
10
20
30
40
2009
2006
Maximum power limit
20
s
pulse
length
lim
it
Predicted deuterium neutral
beam power of a 125kV/65A
chequerboard PINI
Beam voltage (kV)
Injecteddeuteriumpower(MW)
40 60 80 100 120 140
0.0
0.5
1.0
1.5
2.0
2.5
130kV/56A PINI (Supercusp)
125kV/65A PINI (Chequerboard)
2.2 MW
125kV
• neutral beam performance:
23MW x 10 seconds
=> 34MW x 20 seconds

19. The Neutral Beam Enhancement Project
Related contracts: Art7 (23.7M)
- Power Supplies JEMA(12.2+4.5M)
- 36keV ABB(1.5M), lintronics(565k), Resistor HVR (226k)
-PINI PVA (195k), extr. Grids Galvano (425k)
- Neutralisers PVA(562k)
-Beam stop Accel(715k), Cooled duct Accel(2.8M)

20. Ion sources and PINIs

21. • Major role of the Duct Scraper Assembly is to
provide Duct Liner protection against power
loading from re-ionised particles.
• Re-ionised particles produced in the duct are
focused in vertical and radial fringe fields from
the tokamak poloidal field coils.
• Power densities can become high (~5MW/m²).
• Design solution:
multiple hypervapotron assembly
NBE - actively cooled duct liner

22. Vertical Stabilisation
Spare slides

23. Motivation
Avoidance of ELM triggered Vertical Displacement Events VDE
Plasma control: improved vertical
stabilisation for ELM resilience (2008)
Required Upgrades
 3x increase in radial field amplifier power => Enhanced Radial Field
Amplifier (ERFA)
 Improved/faster plasma speed observer
 Faster controller hardware
Study of scenarios with large ELMs in JET limited by high force
disruptions:
response to the ELM produces a radial field excursion
larger than the Fast Radial Field Amplifier (FRFA) current limit =>
VDE
See V Toigo, P1-E-309

24. Vertical Stabilisation Modelling, Analysis and Controller Design:
Features: design of a new optimised controller; Simulation of the closed loop system, including
new Power Supply
Status: Full closed loop model available and validated; design of VS controller started
Planning:
• 2007: Experimental benchmark of new Observer/Control System
• 2008: Reviewed Design of Optimal Observer of VS feedback quantities
• 2009: Inclusion of the new ERFA model in the open and closed loop model
Vertical Stabilisation Controller Hardware and Software:
Features: design and SW/HW implementation of the new controller and integration with the new
Power Supply
Status: new VS Hardware managed by CODAS; High level cubicle design completed; design of new
elelectronics completed
Planning:
- 2007: manufacture and test new electronics; complete new cubicle; Demonstration of VS closed
loop control of FRFA
- 2008: Installation and Commissioning of the new Controller: Hardware and Software.
- 2009: new Closed Loop Control, for new power supply (ERFA); Final adjustments of the new
Hardware
- 2010: Commissioning of all the new system during the restart of JET
Plasma control Upgrade

25. Features:
• Four Series Units ; ±5ka Output Current (FRFA ±2.5ka); ±3kv Output
Volts Per Unit (FRFA ±2.5kv)
• frequency response 100µs (FRFA 200µs)
• Two Quadrant Chopper Controlled (FRFA Four Quadrant)
• 60s Operation At 100% Power (FRFA 70%)
Status:
technical specif. and tender evaluation done, supply contract being
prepared
Planning:
2007: start procurement, engineering design;
2008: manufacture and tests in the factory;
2009: Installation and test at JET
Plasma control Upgrade

26. New fast pellet injector
Spare slides

27. High Frequency Pellet Injector for ELM control and deep fuelling
Pelin Injector
(Tore Supra
design)
toward roots
group
Selectors
Valves
Main
support
frame
Microwave
cavities
Collector
Turbo
pumps
LFS, HFS, VHFS
tracks
Provide deep fuelling capability
Control Type I ELMs
Size Velocity Frequency
35-70mm3
100-500m/s < 15Hz
1-2 mm3
50-200m/s < 40Hz
Operation in Restart 2008

28. EP2 diagnostics
Spare slides

29. Diagnostics for the new pellet injector
• New fast camera (wide angle view) for ablation studies (and edge turbulence
observation):
CMOS camera manufactured, new test image intensifier agreed together with upgrade of opto-
mechanical design
Diagnostics for the ITER-like wall
• Edge and wall diagnostics (erosion, co-depositions, temperature. Same diagnostics
as in EP1):
design and manufacture work performed on QMB system, deposition monitors, wall inserts and index able
collectors
• Spectroscopy (Beryllium and Tungsten in core and edge plasma):
Optical fibres installed for all systems; Completed design of spectrometer room and building work started;
All Art. 7 Contracts signed; execution started for most of them
• Upgrade of the top view IR-system:
camera manufactured and delivered, design of support structure approved by JOC. Optical components
procured and calibrated.
• Cellular Nonlinear Network technology (image processing applied to IR
thermography):
software development progressing, integration into JET network started with CODAS
EP2 Diagnostics: work in progress
IPPUKAEA ENEAFZJ VR
ISCIEMAT HAS CEA USA

30. Burning plasma diagnostics
• Compact neutron spectrometer with organic scintillators:
procurement of spectrometer launched
• Neutron measurements using artificial CVD diamond detectors: installed
• Data acquisition systems for neutron & γ-diagnostic enhancements:
launched
• Upgrade of γ -ray spectrometers:
all procurements under Art. 7 Contracts launched, some delivered
• Neutron Attenuators for γ -ray cameras:
scheme engineering design for vertical and horizontal camera attenuators finalised. Decision taken to
launch installation at JET
• Neutral Particle Analyser detector development and upgrade:
First results of R&D test of new detectors promising. Decision on installation at JET targeted April 08
• UV measurements using single artificial CVD diamond detectors:
first detector installed
• Radiation hard hall probes:
detailed design being finalised. Installation foreseen for March/April 08
EP2 Diagnostics: work in progress
ENEAUKAEAISTMEdC VR TEKES IPP-CR Ukraine

31. Profile (edge) and control diagnostics
• ECE extension (upgrade of the KK3 Heterodyne
Radiometer):
main components delivered and being installed
• Edge LIDAR detector and digitiser upgrade:
new oscilloscope and new detectors installed
objectives ≈ 1cm spatial resolution (equivalent to 6cm in ITER)
• Real time control related diagnostic upgrades
• Upgrade of Li-beam Intensity:
enhancement of performances,transfer function and time resolution
EP2 Diagnostics: work in progress
IPPISTUKAEACIEMAT HASCEA

32. Wall diagnostics: for erosion/deposition studies
Erosion marker tiles in
main chamber and
divertor
Material deposition
+ post mortem tile analysis
Material erosion
A large set of dedicated erosion/deposition probes have
been recently installed / will be refurbished in 2009
Beryllium Tile
Metal interlayer
Be layer

33. Wall diagnostics: ITER-relevant Infra-Red detection
Power losses observed in main
chamber during ELMs and
disruptions - under study
New wide angle IR camera operational
reflective optical components (high neutron irradiation)
Further IR measurements needed:
- High resolution (spatial and temporal) in
divertor
⇒ new camera under construction for
2007
- W and Be compatible IR measurements
⇒ need for ITER-relevant developments:
at present, use of thermocouples
foreseen
⇒ further diagnostics under
consideration
See
A Murari, O4A-D-154
E Gauthier P1-D-479

34. spectroscopy for Be & W:
-Improved visible
-XUV
- VUV
Plasma core and walls
Upgrade of Be and W impurity diagnostics

35. Physics and T retention
Spare slides

36. Tritium retention: a serious issue for ITER
• 0.01- 0.2 g T injected per pulse in T experiments
• up to 17% of T retained in CFC, C-flakes and dust during DTE1 in
1997
• during TTE in 2003 different strike-point position in divertor led to
different distribution of retained T, but T-retention not suppressed
T-retention should be kept low (< a few %) to allow several hundred
full performance pulses before T clean-up becomes unavoidable
⇒ Avoid/minimise Carbon in plasma facing components
⇒ Need to study T-retention with W and Be PFCs
• ~ 50 g T injected per pulse
• Operation suspended once 1000 g T accumulated (350 g T
being the design limit)
ITER
JET

37. • W behaviour under melting
conditions
• W melting and subsequent
plasma operation
W divertor: some specific issues
Large JET ELMs enable
studying W melting
αW
Study of Be-W mixing
Be–W alloying
enhanced W-sublimation/
erosion?
effect on fuel retention?
Liquid
Solid

38. Overall JET-ITER R&D picture
Spare slides

39. Plasma scenarios
in ITER
configuration
•Heating Power Upgrade
•Plasma control upgrade
•Diagnostics & Real Time
Control
•Pellet injector (ELM pacing)
•ITER-like wall
•Wall diagnostics
•Detritiation
techniques
Plasma scenario
compatibility
DT
test of fully
wall-com
patible
scenarios
Confirm
ation
of
reduced
T-retention
ITER-like
wall
experiment
DT
integrated
experiment
JET Required Enhancements

40. ITER-like wall: Key objectives
• TRITIUM
• Tritium retention in re-deposited mixed metal layers
• Tritium inventory control
• WALL LIFETIME
• Material erosion and migration (e.g. effect of Be on W
erosion)
• Metallic Wall lifetime
• Study of damage due to transients (ELMs and
disruptions) e.g. melt layer loss studies
• Refine control / mitigation techniques
 Limit disruption / ELM and mitigate potential damage
• PLASMA SCENARIOS

41. After EP2 ?
Spare slides

42. Experiments
cvcv
Start 2011 Start 2012
• Commissioning of
existing and new
systems
• Includes full technical
commissioning of NB
upgrade
Technical
Restart
17w 3w 18w9w 12m4w 18w
Up to 18m
Specific HLC
• PNB reaching
35MW in safe
operating
modes
• Experiment
s dedicated
to PWI
studies prior
to
intervention
to remove
sample tiles
• Full power
ILW-compatible
scenarios
• Dedicated
ITER scenario
studies
• Possible melt-
layer studies
• Intervention
• Restart
possibility for
TTE-like
operation
Plasma
Restart
9w 3w 9w 3w 9w 3w 9w 3w 9w
Start 2013
Increasing heating power,
pulse length and density range
• Final tech preps
for DT
• DT restart (3y
after start of DT
technical
preparations)
• Plasma
preparations for
DT
• DT operation
• Intervention
Start 2014 End 2014
• RF/LH
dominated
• Commissioning
consistent with
specific scientific
aims
• Start of PWI
studies
Roadmap for exploitation