Transcript Fusion Technology at CIEMAT Overview of Material Irradiation Activities A. Ibarra RaDIATE Collaboration Meeting .

Fusion Technology at CIEMAT
Overview of Material Irradiation Activities
A. Ibarra
RaDIATE Collaboration Meeting . May 19, 2014
CIEMAT
 CIEMAT is a public research
entity focused on energy and
environmental problems,
founded more than 50 years
ago (initially focused on
nuclear research).
 Several centres around Spain
(main one in Madrid). Staff of
around 1500 people and yearly
budget around 100 M€.
 CIEMAT activities are organized
in 5 technical departments
(ENERGY, FUSION,
ENVIRONMENT, TECHNOLOGY,
and BASIC RESEARCH) and 3
transversal departments.
RaDIATE Collaboration Meeting . May 19, 2014
Fusion National Laboratory (FNL)
 The FNL of CIEMAT carries out R&D for the development of magnetic confinement fusion as a
future energy resource and coordinates the Spanish fusion research carried out as part of the EU
Fusion Programme.
The main goals of the Spanish
fusion programme are:
 The development of the
“stellarator” concept, through
the exploitation of the TJ-II
device
 The participation in the large
world fusion experiments (JET,
LHD, W7X, ITER, JT60 and
IFMIF)
 The development of
knowledge and technologies
needed for DEMO and the
Power Plant.
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Fusion activities started at CIEMAT as early as 1975
Around 150 people is working presently in fusion-related
activities at CIEMAT (plus 150 more distributed in other
research centers)
The TJ-II sterellator started operation in 1997
Presently is the only one in EU and the 2nd biggest in the world
CMAM, 02/04/2009
RaDIATE Collaboration Meeting . May 19, 2014
Fusion Technology activities
Activities on Fusion Technology started many years ago (early 80´s) around the study of
radiation effects on insulator materials. Only recently a significant expansion take place.
Presently, around 50 people at CIEMAT and 70-80 distributed in other research centers.
The different research activities are focused along the following lines:
 DEMO Design (mainly breeding blankets)
 Development of breeding blankets technologies (mainly those related to
liquid metals)
 Fusion Materials Fusion Development (Functional and Structural materials,
including production and characterization including irradiation effects)
 Modelling, mainly of radiation damage effects
 New facilities
 Participation in the IFMIF/EVEDA project
 Development of new Spanish Facilities for fusion
RaDIATE Collaboration Meeting . May 19, 2014
Fusion Technology activities
Most of the activities carried out at the CIEMAT group have a common
background: the study of the radiation effects
 Modelling and validation experiments
 Evaluation of damage, MD, Montecarlo methods, rate theory methods
 Benchmarking experiments (resistivity recovery, desorption, …)
 Physical phenomena during irradiation (RIC, RIED, FL, OA, RL, RID, …)
 Radiation effects on structural materials
 Development of new irradiation facilities
 IFMIF
 Ion irradiation
RaDIATE Collaboration Meeting . May 19, 2014
New irradiation facilities
RaDIATE Collaboration Meeting . May 19, 2014
Presently there are no irradiation sources similar equivalent to DEMO
IFMIF Project
To better understand radiation
effects in materials, to be able to
make predictions
Spain heavily involved through the
IFMIF-EVEDA Project included in
the BA Agreement
RaDIATE Collaboration Meeting . May 19, 2014
Electron, Gamma and Ion Irradiation Facilities
2 MeV Van de Graaf electron Accelerator
60 keV Ion Implantator
Collaboration with CMAM (UAM)
5 MeV Tandem Accelerator
NAYADE: Co60 γ-source
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Radiation Enhanced Permeation Chamber.
Radiation Enhanced Desorption Chamber.
Very significant capabilities for
in-beam measurements (later)
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implantation beam line of CMAM
(I) Design and prototyping of an energy
degrader for triple beam irradiations.
 Design and manufacture of a ion beam energy
degrader (H: 3.8 MeV; He: 15 MeV).
 Rotating wheel with 10 Al sheets of different
thicknesses (0 - 50 µm).
(II) Development of the implantation beam line
and a sample holder at CMAM
 Completed and tested a sample holder (useful area
of 10 x 10 cm2).
 Wide range of temperature (LN2 to 500 C)

 4 Faraday Cups to control the beam current during
the scanning. Irradiation test performed on steels,
studying the beam scanning with Luminescent
Silica, with very satisfactory results.
RaDIATE Collaboration Meeting . May 19, 2014
Techno
Fusión
TF-triple beam facility
Presently in standby, but conceptual design is finished and available
A Facility to contribute to the evaluation of
radiation effects on fusion materials
Three simultaneous ion accelerators will
emulate the neutron irradiation effects
Includes:
Two light ions tandem-type, electrostatic accelerators
(mainly for He and H irradiation)
One heavy ion cyclotron (isochronous type) accelerator (Fe
-400 MeV-, W -400 MeV-, Si -300 MeV-, C -100 MeV-, … and
k = 110)
Also experiments under high-field magnet
Irradiation volume up to tens of microns –relevant for
volume effects-
Physical phenomena during irradiation
 Generally speaking, physical properties of materials
(specially non-metallic materials) are different during
irradiation
 For example: electrical conductivity (RIC), optical
absortion (RIA), dielectric properties,…
 And a lot of new phenomena can appear: radiation
induced diffusion, radiation induced electrical
degradation (RIED), radioluminescence, radiation
induced corrosion,…
RaDIATE Collaboration Meeting . May 19, 2014
KS-4V
4 10 -7
Deuterium release rate (mbar l/s)
Deute rium loade d during irradiation.
3,5 10 -7
3 10 -7
2,5 10 -7
2 10 -7
1,5 10 -7
1 10
Loaded without irradiation
-7
5 10 -8
0
0
Irradiation chamber
and accelerator.
100
200
300
400
500
600
700
800
o
T ( C)
Radiation enhanced deuterium
absorption for KS-4V.
RaDIATE Collaboration Meeting . May 19, 2014
Ionoluminescence Si+4 implanted silica
t x 3sec empieza en t_5
KU1 Si+4 24,3 MeV
3, 6 , 9s max1,9eV, 30, 60s max2,7eV
KU1_Si24MeV
2000
2000
KS4V_Si24
I (a.u.)
1500
1000
48s
18s
9s
6s
3s
500
0
1,5
2
2,5
3
1000
39 s
18 s
9s
3s
150 s
1500s 25min
3000s 50 min
500
3,5
4
0
1,5
4,5
Energy (eV)
2
2,5
3
3,5
4
4,5
eV
I301 Si+4 24,3 MeV
I301_Si24MeV
2000
1500
I (a.u)
Intensity (a. u.)
1500
KS-4V Si+4 24,3 MeV
IL measured during ion irradiation to study the
evolution of different defects
t_0 (5s)
t_1 (10)
t_10 (50)
75 s
500 s
5000s
50 s
10 s
5s
1000
500
0
1,5
2
2,5
3
3,5
4
4,5
RaDIATE Collaboration Meeting . May 19, 2014
Fused silica: Optical Absorption
comparison
100
1022 n/m2
(fill symbols)
1
1021 n/m2
(hollow symbols)
0.1
2
3
Gamma irradiated (23.8MGy)
10
OD/cm
10
OD/cm
gamma irradiated (23.8MGy)
neutron irradiated
Neutron
irradiated
100
4
5
KU1
KS-4V
I301
1
0.1
6
2
3
Energy (eV)
30
8
KU1
-1
18
12
6
6
KS-4V
H102
HOQ310
I301
 (cm )
Thermal stability of
gamma irradiation
induced E´ defect
(5.8eV) for different
fused silicas
5
Energy (eV)
10
24
4
S300
6
S312
4
2
0
0
200
400
600
Temperatura (C)
800
0
0
200
400
600
800
RaDIATETemperatura
Collaboration(C)
Meeting . May 19, 2014
Radiation effects on structural
materials
RaDIATE Collaboration Meeting . May 19, 2014
Evaluation of He and self-ion implantation
on EUROFER97 and EU-ODS EUROFER by
nanoindentation and TEM
- He
- EUROFER & EU-ODS - 3-15 MeV at RT,
1,67e15 ions/cm2, 0.625 appm He/s
 Nanoindentation on  Nanobubbles
transversal surface.
observed in both
Measuring increase in
steels with a size
hardness due to
around 2 nm.
increment in He.
6.0
EU-ODS EUROFER He implanted
EUROFER'97 He implanted
6.0
Implanted
Implanted
Unimplanted
5.5
5.5
5.0
5.0
Hardness [GPa]
Hardness [GPa]
750 appm He
4.5
4.0
3.5
Unimplanted
4.5
4.0
3.5
3.0
3.0
2.5
2.5
0
10
20
30
40
Distance from interface [m]
50
60
0
10
20
30
40
50
60
Distance from interface [m]
Hardness increase observed in both steels, being more pronounce on EUROFER97.
RaDIATE Collaboration Meeting . May 19, 2014
Evaluation of He and self-ion implantation
on EUROFER97 and EU-ODS EUROFER by
nanoindentation and TEM
Fe implantation:
EUROFER & EU-ODS 0.05 to 30 dpa at RT.
Comparative study on mechanical
properties between EUROFER97 and
EU-ODS EUROFER in as received, 0.2
and 6.5 dpa status.
From 10 to 30 dpa: in progress.
Nanoindentation on normal
surface to ions
EU-ODS EUROFER
EUROFER
10
As received
0.2 dpa
6.5 dpa
9
10
10
9
9
10
As received
0.2 dpa
6.5 dpa
9
8
7
7
7
6
6
6
6
5
5
4
4
Hardness (GPa)
8
7
8
Hardness (GPa)
Dislocation network due to self
ion irradiation
8
5
5
4
4
3
3
3
3
2
2
2
2
1
1
1
1
0
0
500
0
0
50
100
150
200
250
300
350
Penetration depth (nm)
400
450
0
50
100
150
200
250
300
350
400
450
Increase in hardness
observed in EUROFER97.
EU-ODS EUROFER shows
more resistance to the
same damage.
0
500
Penetration depth (nm)
RaDIATE Collaboration Meeting . May 19, 2014
Modelling
RaDIATE Collaboration Meeting . May 19, 2014
Radiation damage evaluation and its comparison
with the expected damaged by neutrons in a fusion reactor
A methodology to calculate damage (PKA spectra and, consequently, dpa and
He, H generation) for different radiation sources (neutrons, ions,…electrons?)
has been developed
 A combination of neutron
Al2O3
transport codes
(MCNP5/MCNPX),
processing of nuclear
libraries (NJOY) and
approximation of binary
collisions (MARLOWE) is
used.
 MARLOWE code has been
modified to estimate the
stopping of ions in materials
with energies of MeV (or
even GeV).
 This methodology is also
able to take into account
recombination of defects by
means of an effective
capture radius I-V (based on
MD calculations).
RaDIATE Collaboration Meeting . May 19, 2014
Molecular Dynamics:
The case of H-He-V in Fe
Large amounts of H and He form in steels under neutron irradiation and agglomerate
with vacancies into bubbles.
Cluster H2HeV in Fe
Binding to HeV5Hm
4,0
Bubble of H-He in Fe
Binding energy (eV)
3,5
3,0
2,5
He
V
H
2,0
1,5
1,0
0,5
0,0
0
1
2
3
4
5
Nb H atoms
 With MD it is calculated the binding energy of H, He and V. This allows to calculate the
frequency at which they dissociate, which is used in kinetic models (OkMC or Rate Theory).
 MD calculations reveal the structure of H-He bubbles. He is contained in a core (red spheres),
surrounded by a shell of H atoms (blue spheres).
RaDIATE Collaboration Meeting . May 19, 2014
A GPU-Object kMC for the evolution of defects
• The kinetic Monte Carlo is a computer simulation method intended to simulate
the evolution of a set of objects, knowing the type of event those objects can
perform and the probability for each event to occur.
•Can treat difficult issues such as correlation between defects and
inhomogeneities.
• CPU time of classical OkMC simulations too slow (days – weeks). Limited to 100000200000 defects. Only allows to explore small piece of material.
• We explore the possibility to use GPU (graphics card) programming.
Thousands of cores !
Typical OkMC box
~60 nm
Our GPU-OkMC is able to simulate evolution of millions of particles in only few hours.
Allows to simulate evolution of defects in a realistic piece of materials.
RaDIATE Collaboration Meeting . May 19, 2014
Resistivity Recovery Experiments
on Fe-Cr
(III) H+ Irradiation of Fe-Cr samples and its diagnosis by resistivity recovery.
A “Resistivity Recovery (RR)" system has been developed by Ciemat, reaching a new
method of irradiation and measure that provides cleaner results than the classical
method. RR spectra have been obtained in samples Fe100-x Crx (x = 5, 10, 14)
irradiated with H+ of to 5 MeV.
Very important for the experimental validation of the computational simulations of
damage by radiation in steels.
RaDIATE Collaboration Meeting . May 19, 2014
Conclusions
 FT group at CIEMAT has a long tradition on the
study of radiation effects from the point of view
of fusion materials needs
 Our work is organized along the following main
lines: development of new facilities, radiation
effects on functional and strucutural materials,
modelling and validation experiments
 We are open to collaborations if something of
common interest can be identified
RaDIATE Collaboration Meeting . May 19, 2014
Thanks for your kind attention!
RaDIATE Collaboration Meeting . May 19, 2014