Inertial Fusion Energy Materials under...
Transcript of Inertial Fusion Energy Materials under...
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Inertial Fusion Energy Materials under Irradiation
Technology watch workshop on IFE-KiT22 March, 2010 (11:30-18:30)
hosted by Instituto Fusion Nuclear Universidad Politecnica de Madrid (ETSII)
J. M. Perlado
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Inertial Confinement Fusion: Reactor concepts and NIFMATERIALS assessment
– Structural Material :Steel SS304
Lifetime = that of the plant
Flibe: Coolant, T reproduction, and protection
HYLIFE-IINIF
MATERIALS
Target composition
(nanostructures)
First Wall, Optics
Structural, Coolant
Activation and Damage
Heat Deposition, T economy
Effects of:
Neutron
Debris
Shrapnel
X-rays; High T; High P
SOMBRERO
Type of Facility:
Ignition, Reactor/Protection
HiPER
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
MATERIALS FOR TARGETS
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
First results on shockwave generation and propagation on Ta: Pictures show the resulting crystal structure (5 millions of atoms) after 5ps MD. Shock propagates in direction [100].
”Piston” velocities were in the range from 180 Km/s to 720 Km/s. Sample compression reaches 1014 bars.
Advanced Materials
NANOCRYSTAL
METALLIC FOAMS
Advance Manufacturing Techniques in NanoMicrotechnology
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
CENTRAL IGNITIONDIRECT DRIVE – INDIRECT DRIVE
X- Rays Neutrons Ions
Energy
-Direct. Drive-Indirect Drive
1,5%18%
75%75%
23%7%
OPERATIONAL WINDOWS FOR DRY-WALL AND WETTED-WALL IFE CHAMBERS
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Spectra for NRL
Spectra for HY DD
Spectra for ID
X‐ray spectra
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
We don’t have tables!!I asked John!
SHOCK IGNITION
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
1.00E-04
1.00E-03
1.00E-02
1.00E-01
1.00E+00
1.00E-11 1.00E-10 1.00E-09 1.00E-08 1.00E-07 1.00E-06 1.00E-05 1.00E-04 1.00E-03 1.00E-02 1.00E-01 1.00E+00 1.00E+01 1.00E+02
MeV
Prob
abili
ty
constant density in target
high and low density distinction
Neutron Spectra High gain capsule with
2x 1020 neutrons / pulse
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Assuming 4 m Radius
Wall after protection = 1 cm of Fe
DAMAGE
RATEMonteCarlodetailed calculations
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Designing systems by simulation of the timetime--dependentdependent neutron intensities and energy spectra is already well done with existing methodology. This is an example assuming first wall protection (which will be not needed for HiPER operation except experiments in mock-up testing cells could be approved)
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
NEUTRONICS 3D DETAILED CALCULATIONS USING CAD AND MCNPX. It is time to start to use in Inertial Fusion Reactors Concepts and Facilities to get consequences such as Activation /Damage …….defining structures and materials……………………
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
NEUTRON TRANSPORT CALCULATION
HYLIFE-IISpectrum, flux intensity, and average neutron energy in the FSW with 60 cm of Flibe thickness and2240 MW fusion power
1,0E+04
1,0E+05
1,0E+06
1,0E+07
1,0E+08
1,0E+09
1,0E+10
1,0E+11
1,0E+12
1,0E-05 1,0E-04 1,0E-03 1,0E-02 1,0E-01 1,0E+00 1,0E+01 1,0E+02
Energy (MeV)
Flux
Den
sity
(n*c
m-2
s-1 M
eV-1
)
-100
-75
-50
-25
0
25
50
75
100
%D
IF=
(TA
RT-
MC
NP)
/TA
RT*
100
Flux Density TART2000
%DIF ENDFB6.0
%DIF ENDFB6.8
%DIF JENDL3.2
%DIF JEFF3.1
TART2000 MCNP4c2 ENDF/B-VI.0 ENDF/B-VI.8 JENDL3.3 JEFF-3.1 φ (n cm-2 s-1) 5.30E+14 5.69E+14 5.71E+14 6.41E+14 6.18E+14 (MeV) 3.06E-01 3.68E-01 3.69E-01 4.16E-01 3.46E-01
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Selection of Low Activation elementsin HYLIFE-II irradiation conditions
Limits in the concentration (weight fraction) for all natural elements
Acceptability of pure elements under Shallow Land Burial Criteria (SLB)
Elements with good engineering properties but not acceptable froElements with good engineering properties but not acceptable from activationm activationElements as impurities restricted to very severe limitsElements as impurities restricted to very severe limits
DOMINANTS NUCLIDES LIMIT CONCENTRATION RECYCLING RECYCLING
ELEMENT SLB REMOTE HANDS-ON SLB REMOTE HANDS-ONNB NB 94 (100.) NB 94 (100.) NB 94 (100.) 6,93E-07 1,91E-05 4,78E-08 TB H0166M (100.) H0166M (100.) H0166M (100.) 4,82E-06 1,43E-04 3,67E-07
ZN - CO 60 (100.) - NL 7,59E-01 NL
NO limit
100-1000 ppm
1-10%
1-10 ppm
0,1-1% 0,1-1 ppm10-100%
10-100 ppm
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Energy Spectra
Average X-ray energy 8,8 keV
Particles go up to some MeVs
Burning hydrodynamic codes are used to calculate the energy spectra….IN THESE CALCULATONS: Shock target of 48 MJ (J. Perkins). SO CRITICAL TARGET COMPOSITION !!!
REQUIREMENTS FOR TARGET AREA REPETITIVE
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Time distribution of fluence on wall (every 200 ns)
HOW X-RAYS AND IONS ARRIVE TO FIRST WALL TIME DEPENDENT
Physical - Nuclear (up to MJ) and electronic (MJ onwards). It can be studied with SRIM software. MUCH MORE FUNDAMENTAL WORK IS NEEDED!!! Chemical - Reactions on surface (not in Tungsten, very important in carbon containing walls)
Radiation enhanced sputtering – Diffusion of interstitial atoms that diffuse to the surface and sublimate (important in carbon)
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Origin Clusters, Debris, Shrapnel•Produced during the ablation of the target, and ulterior re-emission processes from the chamber itself•Energy and size distribution not available (but for some experiments)
Particles in the nano-scale (clusters)•Sputtering of polyatomic species and clusters is one/two orders of magnitude higher.•No models available. Their effect has to be studied for every specific case.
Particles in the micro-scale (debris)•They appear as deposits/small particles/droplets•Damage up to some microns (crater/erosion)
Particles in the tens of micrometer-scale (Shrapnel)•They appear as “big” fragments•Damage of some hundreds of microns (crater/erosion)
Their effectcan be
modelled usingHypervelocity
Impactsimulations(Autodyn)
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
•Energy deposition•Simulation of the spatio-temporal deposition of energy – FLUKA, MCNPXFLUKA, MCNPX•Thermo-mechanical effects – ANSYSANSYS
(As first approx. we do not accept melting/evaporation of wall)WHEN PROTECTION OR PHASE TRANSITION: FLUENT, CFX FLUENT, CFX
•X-ray damage•A massive photoelectric effect on surface is expected. Damage?
(roughly 5% of X-rays will result in the emission of e-, i.e. 2 x 1016 e-.m-2)•Ion damage
•Sputtering – SRIMSRIM code. The design of target is critical(a 2 mm radius target with 35μm thick plastic surface contains about 2 orders of magnitude more atoms than a monolayer of the 5 m radius tungsten wall; sputtering efficiency of C atoms ≈1-10%)
•Defects resulting in modifications (hardness, corrosion, fracture...). Is there software to simulate those effects available?
•Debris/Shrapnel•Simulation of debris/shrapnel formation•Simulation of damage on wall (micrometeorite impact theory) – ANSYSANSYS
√
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Thermomechanical simulation for the first wall In all the cases studied thermal stress is very far from yield stress, but temperature could be close to melting point (~3695 K) if Pulse energy is higher than 2 J/cm2.
Pulse Energy (J/cm2) Temperature(K) Stress (MPa)1 1800 1.42 3100 2.7
2.8 >4000 3.7
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Ion Number of particles
Average energy (keV)
Sputtering (at/ion)Tungsten
Shots to remove monolayer(Tungsten 1,8E16 atoms/cm2)(5 m radius chamber)
H 1,18E19 143 0 --D 1,05E20 191,4 0 --T 9,45E19 235 0 --3He 1,9E17 296 1% 1e74He 1,7E19 1334 0 --12C 1,38E19 760 4% 2,7e413C 1,15E17 820 10% 1,3e6
In the case of Tungsten and for average kinetic energy particles
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
We have these inputs data, we could get responses with DEPENDENCE OF PROTECTION
Time (s)E
nerg
y (J
)
Time (s)
Tem
pera
ture
(eV
)
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Incoming laser is first deflected and focused in the final opticsChamber wall positioned radially between target and optics with penetrations to allow the entry
High energy neutronsX-RaysChamber black body like
radiation Ion debris
Lens
Mirror
DisposableLens
Pinhole
16 m
8 m
8 m5 m
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
• Integrated energy deposition• Energy contributions orders of magnitude lower than the energy
coming from the laser (~2KJ)• Big uncertainties in photons but we can still get a taste• Local hot spots could appear
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Identification of defects and production under irradiation with / without H.
It is absolutely clear that in both kind of defects, the number of defects, both without H atoms and with H atoms, increases withincreasing PKA energy.
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
MATERIALSMATERIALSCeramics (Windows/Optics): SiO2, Alumina, FCa
First Wall: Be, C, W, Ferritic Steels
Structural: Ferritic Steels (FeCr based), Vanadium Alloys, Composites based in SiC or C fibers.
Nanocrystal material for high T / high P conditions in target design, and through Oxide Dispersion Strength in FeCr Ferritic Steels.
Structural Materials under Irradiation (Neutrons) = FULL COOPERATIVE WORK IN MODELLING AND EXPERIMENTS BETWEEN EFDA AND IFE GROUPS
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
The Grand ChallengeThe Grand Challenge: predict strain localization and work
hardening in irradiated tensile tests
Stress-strain relation of tensile specimens of irradiated Cu (from: M. Victoria et al. 2001)
TEM weak beam
We now have a mesoscale computational tool to study these problems: Strain hardening beyond the formation of channels We will extract DD-based constitutive laws
for material models in FE calculations
Simulation of irradiated copper tensile specimen
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
SiC
J.M. Perlado, L. Malerba, T. Díaz de la Rubia, Fusion Technology, 34, no. 3, part 2 (1998) 840-
847Molecular Molecular DynamicsDynamics: : MacroscopicMacroscopic ApplicationApplicationDefiningDefining StressStress--StrainStrain curvecurve
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• Materials:– Alloys prepared from 99,99 Fe and Cr by arc melting in a
pure Ar atmosphere. Nominal concentrations: 1, 2, 3, 5, 7, 10, 12 y 15% at Cr.
– Effect of Cr content• Ion irradiation conditions
– Irradiations performed in the AIM facility of the Forschungszentrum Dresden-Rossendorf (FZD)*:• Fe+ 150 keV• Dose: 2x1018 ions/m2 (~0.8 dpa)• Flux: 2x1015 ions/m2 s• Temperatures: 140K and 300K
• TEM observation at RT– JEOL 200 keV
140 K
300 K
Irradiation time Observation time
IrradiationTemperature
Experimental methodology in FeCr for EFDA
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Clusters > 100 defectos (≈>2 nm)Computational KMC model
The comparison with experiment is not still correct but is gping with less uncertainty to fox such results
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Radiation Damage in Repetitive Systems Radiation Damage in Repetitive Systems …………There will be There will be consequences in behavior (?)consequences in behavior (?)
Microscopic simulation on defect generation at low doses. Good starting …. ….
NOT ENOUGH
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Generation of Radiations and Beams by High Power laser
超高エネルギー密度プラズマの発生と精密計測
X-ray
γ ray
MeV 電子
MeV イオン
中性子
中間子
陽電子
ペタワットレーザー
実験計測
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ǙDZÇÃÉsÉNÉ`ÉÉǾå©ÇÈǞǽDžÇÕïKóvÇ-Ç�
Laser implosionD+D: 2.4 MeV neutronD+T: 14 MeV neutronD+ 3He: 14Mev Proton
Ultraintense short pulse laser
Neutron,ProtonsX-rays
Gas-cluster target Solid film target
Merit : low debris and high rep-ratesmall laser energy
Demerit: low efficiency
Merit: high efficiencyDemerit: debris
Merit: high efficiencyDemerit: high energy neutron
High energy laser
MeV ionNeutronMeV electronμ-onPositronHard X-ray
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Neutron production Scaling depending on laser energy
Laser pulse energy (J)
Neu
tron
yield/ puls e
Fast ignition
FIREX NIF
11B(p,n)11C
100
104
106
108
1010
1012
1014
1016
1018
1020
0.1 1 10 100 1000 104 105 106 107
ImplosionClusterCD shellNuclear reaction Expected by laser fusion
7Li(p,n)7Be
Exploding pusher
E2.235 fsFalcon
100 fsJanUSP
VULCAN
LHART
Central ignitionQ=1 (DT
)
g-D2
natPb(p,xn)Bi
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Various neutron production processes andenergy efficiency
Type of nuclearreactions
generation efficiencyNeutron/ particle
Energy cost MeV/neutron
235U(n,f) 1n/fission 180
DT fusion 1n/fusion -
D-Be (Ed = 15MeV) 1.2x 10-2 n/d 1,200
Electron beam(Ee=35MeV) 1.7x10-2n/e 2,000
Hg sparation(Ep = 3GeV) 75 n/p 35
P-Be ( Ep =5MeV) 10-4 n/p ? 50,000Li-P ( Ep = 3MeV) 10-4 n/p 30,000
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
Thanks for your attention
and…………….
coming to Madrid !!!!!!!!!!!!!!!!!
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
IFE REACTORS DESIGNS
MAIN THREATS TO THE CHAMBER WALL-High temperatures -> evaporation-Ion implantation (in particular He)-Sputtering, ablation-Mechanical damage (roughening, embrittlement,…)-Neutrons
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
We have / will need to develop an updatedmethodology for IFE accident analyses• In order to maximize the S&E advantages of IFE,
accident consequences must be addressed realistically
• In early studies, safety analysis tools were not very refined which often resulted in overly conservative safety analyses and safety-important design details were not available to incorporate into the safety assessment
• We have adopted and adapted computer codes traditionally used by MFE, and integrated them in a set of state-of-the-art codes/libraries for IFE safety analyses
• These tools have provided the first self-consistent analysis to understand the integrated behavior of an IFE chamber under accident conditions
• We have applied this methodology to various IFE designs and a target fabrication facility, with the goal of demonstrating that fusion designs could meet the no-evacuation objective (1 rem)
HYLIFE-II
SOMBRERO
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid
TART/MCNP input:model geometry,
materials
TARTCHECK:verification of
TART geometry
TART: photon/neutron transport
ENDL: cross-section
library
TARTREAD
ACAB input:irradiation history,
neutron flux, materials, output options
ACAB: activation calculations
Radioactive inventory, afterheat, etc
FENDL/A-2.0: cross-section
library
FENDL/D-2.0: decay library
TART input for γ-ray transport
Photon/neutron energy deposition,
path-lengths
CHEMCON: heat transfer
Time-temperature history
MELCOR input:geometry, radioactive
source term
Radioactivity release fraction
OFF-SITE DOSES
DCF library
MELCOR: thermal-hydraulics
CHEMCON input:geometry, energy
source term= input file
= FORTRAN code
= Data library
= Output data
SET OF COMPUTER CODES AND LIBRARIES
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March 22, 2010 EFDA IFE KIT Meeting / Instituto Fusion Nuclear / ETSII / UPM / Madrid