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Nuclear damage Parameters
for SiC/SiC Composite in
Fusion Systems
Mohamed Sawan
Fusion Technology Institute
The University of Wisconsin-Madison
International Symposium on Silicon Carbide and Carbon-Based
Materials for Fusion and Advanced Nuclear Energy applications
January 19-22, 2009
Daytona Beach, FL
Yutai Katoh, Lance Snead
Materials Science and Technology Division
Oak Ridge national Laboratory
Much Harder Neutron Spectrum
in Fusion Compared to Fission
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
10
5
10
7
10
9
10
11
10
13
10
15
10
-2
10
0
10
2
10
4
10
6
10
8
Fission Reactor
Fusion Reactor FW
NeutronFluxperGroup(n/cm
2
s)
Neutron Energy (eV)
46 Energy Group Structure
Neutron spectra normalized to
10
15
n/cm
2
s total flux
Average Energy
Fission 0.7 MeV
Fusion 2.7 MeV
Fusion 14.1
MeV Peak
Fusion Lacks
Significant Thermal
Component
He/dpa ratio is significantly higher than in a fission
reactor nuclear environment (~10 vs. ~0.3 for FS)
Effect more pronounced for SiC (~90 vs. ~1 for SiC)
Application of SiC/SiC
Composites in Fusion Systems
SiC/SiC composites have been considered for use in fusion systems
Because of their low induced radioactivity and high temperature
operation they represent an attractive candidate for structural material
They have been proposed as structural material for FW and blanket in
several MFE and IFE designs
SiC/SiC composite is the preferred structural material for FW and
blanket of the HAPL IFE design with magnetic intervention
SiC/SiC composites are considered for use as flow channel inserts (FCI)
in dual coolant lithium lead blanket (DCLL). They provide electrical
insulation to mitigate MHD effects and thermally isolate the high
temperature LiPb from the low temperature helium cooled FS
Lifetime of SiC/SiC composites in fusion radiation environment is a
major critical issue
Radiation effects in fiber, matrix, and interface components represent
important input for lifetime assessment
Impact of radiation on insulating properties of FCI is also a critical issue
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
High Average power Laser
(HAPL) Conceptual Design
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
• Direct drive targets
• Dry wall chamber
• 40 KrF laser beams
• 367.1 MJ target yield
• 5 Hz Rep Rate
• 6 MW/m2 peak NWL
Dry wall must accommodate ion and
photon threat spectra from target
Extreme flux of intermediate energy
ions pose a significant issue of
extremely high pulsed temperatures
and erosion/ablation of FW
Magnetic intervention used to steer
ions away from chamber wall
Large fraction of magnetic energy can
be dissipated in chamber walls if an
electrically resistive structural material
is used (SiC/SiC)
LiPb or Flibe self-cooled blankets used
1 cm Be insert used in FW coolant
channel with Flibe for tritium self-
sufficiency
Nuclear Analysis for SiC/SiC in
Fusion Environment
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Radiation parameters determined for SiC/SiC composites for MFE and
IFE systems
Configurations of ARIES-AT advanced tokamak and HAPL laser fusion
conceptual designs were used
ARIES-AT HAPL
Calculation of damage
Parameters
Rates of dpa, He production, H production, and % burnup calculated
for both sublattices of SiC fiber/matrix and interface material
The cross section library includes all partial reaction cross sections
required to determine gas production and transmutations
The library includes the damage energy cross sections needed to
determine the atomic displacements
Used recommended displacement energies for SiC, namely 20 and 40
eV for the C and Si sublattices, respectively
Leading interface material candidates are graphite and multilayer SiC
Damage parameters for the SiC interface material are identical to
those for the SiC fiber/matrix
Damage parameters for the graphite interface material are same as
those for C sublattice of SiC except for dpa due to the higher (30 eV)
displacement energy
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Peak Damage Parameters in
OB SiC/SiC FW of MFE System
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Flibe Blanket
LiPb Blanket
Observations on Peak Damage
Parameters in MFE System
dpa rates in C and Si sublattices of the SiC fiber/matrix
are comparable
dpa rate in graphite interface is 33% lower than in C
sublattice of SiC
He production rate in C sublattice of SiC and graphite
interface is about a factor of 4 higher than in Si sublattice
of SiC and is dominated by the (n,n´3 ) reaction
He production rate in graphite interface is 60% higher
than average He production rate in the SiC fiber/matrix
Significant hydrogen production occurs in Si with a
negligible amount produced in C
Burnup rate of Si sublattice is twice that for C sublattice of
SiC fiber/matrix and graphite interface
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Comments on Burnup of SiC
Burnup of Si sublattice is about a factor of 2 more
than that for C sublattice
The burnup is equivalent to introducing impurities in
the sublattices of the SiC
Property degradation depends on the kind of
impurities introduced
Transmutation of Si produces primarily Mg and Al
with smaller amount of P and main transmutation
product for C is Be with smaller amount of B and Li
Nonstoichiometric burnup of Si and C is expected to
be worse than stoichiometric burnups and could be
an important issue for SiC
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Impact of Breeder/Coolant on
SiC/SiC Damage Parameters
10-3
10-2
10-1
100
101
102
103
104
0 10 20 30 40 50 60 70 80
dpa/FPY in PbLi blanket
He appm/FPY in PbLi blanket
dpa/FPY in Flibe blanket
He appm/FPY in Flibe blanket
DamageRateinSiC
Depth in Blanket (cm)
Outboard in MFE Reactor
Neutron Wall Loading 6 MW/m
2
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Peak dpa values with Flibe are
about half those with LiPb
Peak gas production and
burnup rates with Flibe are
higher by 3-10% than with
LiPb
dpa values with Flibe have
steeper radial drop compared
to that in LiPb blanket while
gas production and burnup
rates have slightly less steep
radial drop
Flibe is more effective
attenuating intermediate
energy neutrons while LiPb is
more effective attenuating
high-energy neutrons
Neutron Energy Spectra at FW
for LiPb and Flibe Blankets
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Harder spectrum with Flibe
Larger total neutron flux with LiPb
due to increased secondary neutron
production from Pb that are mostly
in the 10 keV to 2 MeV range
These intermediate energy neutrons
result in higher dpa with LiPb
High energy flux (E>2 MeV) is much
smaller with LiPb resulting in lower
gas production and burnup rates
10
4
10
6
10
8
10
10
10
12
10
14
10
-2
10
0
10
2
10
4
10
6
10
8
PbLi Blanket
Flibe Blanket
NeutronFluxperEnergyGroup(n/cm
2
s)
Neutron Energy (eV)
Energy spectrum at first wall
OB in MFE reactor
6 MW/m
2
neutron wall loading
175 Energy Groups
Different Features of IFE Systems
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Significant geometrical, spectral and temporal differences
between IFE and MFE systems affect radiation damage levels with
impact on lifetime assessment
Geometrical differences:
Point source in IFE Source neutrons in IFE chambers impinge on
the FW/blanket in a perpendicular direction For same NWL,
lower radiation effects at FW with smaller radial gradient in blanket
Point
source at
target
FW
FW
Volumetric
source in
plasma
IFE
Chamber
MFE
Chamber
Different Features of IFE Systems
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Energy Spectrum for
Neutrons Emitted
from HAPL Target
Combined geometrical and
spectral differences impact
time-integrated radiation
damage parameters
Simple scaling of radiation
effects with neutron wall
loading between IFE and MFE
systems is inappropriate
Spectral differences:
• Fusion neutron interactions in compressed IFE target result in
considerable softening of neutron spectrum incident on the FW/
blanket in IFE chambers
• Softened source neutron spectrum with 10-13 MeV average energy
depending on target R with some neutron multiplication (~1.05)
Peak Damage Parameters in
SiC/SiC FW of HAPL
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Flibe Blanket
LiPb Blanket
Comparison between FW
Neutron Spectra in IFE and MFE
Calculated total neutron flux values at FW are nearly identical
in both systems for the same NWL
Spectrum is softer in IFE system with average energy of 1.66
MeV compared to 2.67 MeV in MFE system
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
10
4
10
6
10
8
10
10
10
12
10
14
10
-2
10
0
10
2
10
4
10
6
10
8
IFE
OB in MFE
NeutronFluxperEnergyGroup(n/cm
2
s)
Neutron Energy (eV)
Energy spectrum at first wall
PbLi blanket
6 MW/m
2
neutron wall loading
175 Energy Groups
10
10
10
11
10
12
10
13
10
14
10
15
10
6
10
7
IFE
OB in MFE
NeutronFluxperEnergyGroup(n/cm
2
s) Neutron Energy (eV)
Energy spectrum at first wall
PbLi blanket
6 MW/m
2
neutron wall loading
175 Energy Groups
Comparison between FW Damage
Parameters in IFE and MFE
• Peak values for the same neutron wall
loading are significantly different
• Gas production and burnup rates are about a
factor of 2 lower in IFE system compared to
that in MFE system with the same NWL
• The peak dpa rate in IFE is lower than that in
the OB region of MFE by ~7% for LiPb
blanket and ~20% for Flibe blanket
• These differences are due to geometrical and
spectral differences between IFE and MFE
systems
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Pulsed Effects in IFE Systems
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
In IFE chamber neutron source has a pulsed
nature
Energy spectrum of neutrons from target results
in time of flight spread and backscattering from
blanket extends period over which a particular
radiation effect takes place
Time spread is larger for radiation effects
produced by lower energy neutrons (time spread
of dpa larger than that for gas production and
transmutation)
Pulsed Effects in IFE Systems
(Cont’d)
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Peak instantaneous damage rates in IFE FW/blanket
are ~5 to 8 orders of magnitude higher than steady
state damage rates produced in MFE systems
Difference in time spread results in higher
instantaneous He/dpa ratios in IFE systems
compared to MFE systems
Time dependent neutronics analysis is necessary for
subsequent microstructure evolution analysis
Analysis is underway to determine pulsed
instantaneous damage parameters in SiC/SiC FW of
HAPL and couple results with microstructure
evolution analysis
Pulsed Damage parameters in
HAPL SiC/SiC FW
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Temporal peaking factor is significantly higher for He production than
for atomic displacement (8.7x107 vs. 1.1x107)
Peak instantaneous He/dpa ratio is much higher than that determined
from the temporal average (cumulative) values (368 vs. 47)
Use of SiC FCI as Insulator in
DCLL Blanket
• The Dual Coolant Lithium Lead (DCLL) blanket concept is the
preferred US blanket concept for commercial fusion plants
• It provides a pathway to high outlet temperature with current
generation structural materials
• A key element is use of SiC (foam or composite) flow channel
inserts (FCI) for electrical and thermal insulation
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Peak Damage Parameters in
SiC FCI of DCLL Blanket
Neutronics calculations for the DCLL concept in OB region of
MFE system with a NWL of 6 MW/m2
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
Relative values for different constituents are similar to those
obtained for the SiC/SiC FW of self-cooled LiPb blanket
Damage parameter values are lower by ~40% due to
attenuation in the 3 cm thick He-cooled ferritic steel FW
Metallic Transmutation
Products in SiC FCI
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna
FCI is not a structural element and main concern is degradation in its primary
role as electrical and thermal insulator
Degradation in resistivity results from introduction of metallic transmutation
products
Transmutation calculations using the ALARA code determined rate of build-up
of different metallic transmutation products
00
1000
2000
3000
4000
5000
0 0.5 1 1.5 2 2.5 3 3.5
Li
Be
B
Mg
Al
P
TTransmutationProduction(appm)
Operation Time (FPY)
6 MW/m
2
Neutron Wall Loading
Front Layer of SiC FCI
in DCLL Blanket
Dominant metallic transmutation
product is Mg that builds up to
~0.43 at% concentration at the
expected lifetime of a DCLL
blanket in a fusion power plant
It is essential to assess impact of
these levels on electrical and
thermal conductivities of FCI to
determine if it will restrict
lifetime of the DCLL to less than
that determined by radiation
damage to ferritic steel FW
Conclusions
• Radiation damage parameters in SiC/
SiC composite have strong dependence
on the blanket design (coolant,
breeder) and plasma confinement
approach (MFE, IFE)
• Input needed from materials
community regarding appropriate
lifetime criterion
M. Sawan
1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices”
2-5 Dec 2008, IAEA, Vienna

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Nuclear damage parameters for SiC composites in fusion system

  • 1. Nuclear damage Parameters for SiC/SiC Composite in Fusion Systems Mohamed Sawan Fusion Technology Institute The University of Wisconsin-Madison International Symposium on Silicon Carbide and Carbon-Based Materials for Fusion and Advanced Nuclear Energy applications January 19-22, 2009 Daytona Beach, FL Yutai Katoh, Lance Snead Materials Science and Technology Division Oak Ridge national Laboratory
  • 2. Much Harder Neutron Spectrum in Fusion Compared to Fission M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna 10 5 10 7 10 9 10 11 10 13 10 15 10 -2 10 0 10 2 10 4 10 6 10 8 Fission Reactor Fusion Reactor FW NeutronFluxperGroup(n/cm 2 s) Neutron Energy (eV) 46 Energy Group Structure Neutron spectra normalized to 10 15 n/cm 2 s total flux Average Energy Fission 0.7 MeV Fusion 2.7 MeV Fusion 14.1 MeV Peak Fusion Lacks Significant Thermal Component He/dpa ratio is significantly higher than in a fission reactor nuclear environment (~10 vs. ~0.3 for FS) Effect more pronounced for SiC (~90 vs. ~1 for SiC)
  • 3. Application of SiC/SiC Composites in Fusion Systems SiC/SiC composites have been considered for use in fusion systems Because of their low induced radioactivity and high temperature operation they represent an attractive candidate for structural material They have been proposed as structural material for FW and blanket in several MFE and IFE designs SiC/SiC composite is the preferred structural material for FW and blanket of the HAPL IFE design with magnetic intervention SiC/SiC composites are considered for use as flow channel inserts (FCI) in dual coolant lithium lead blanket (DCLL). They provide electrical insulation to mitigate MHD effects and thermally isolate the high temperature LiPb from the low temperature helium cooled FS Lifetime of SiC/SiC composites in fusion radiation environment is a major critical issue Radiation effects in fiber, matrix, and interface components represent important input for lifetime assessment Impact of radiation on insulating properties of FCI is also a critical issue M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna
  • 4. High Average power Laser (HAPL) Conceptual Design M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna • Direct drive targets • Dry wall chamber • 40 KrF laser beams • 367.1 MJ target yield • 5 Hz Rep Rate • 6 MW/m2 peak NWL Dry wall must accommodate ion and photon threat spectra from target Extreme flux of intermediate energy ions pose a significant issue of extremely high pulsed temperatures and erosion/ablation of FW Magnetic intervention used to steer ions away from chamber wall Large fraction of magnetic energy can be dissipated in chamber walls if an electrically resistive structural material is used (SiC/SiC) LiPb or Flibe self-cooled blankets used 1 cm Be insert used in FW coolant channel with Flibe for tritium self- sufficiency
  • 5. Nuclear Analysis for SiC/SiC in Fusion Environment M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Radiation parameters determined for SiC/SiC composites for MFE and IFE systems Configurations of ARIES-AT advanced tokamak and HAPL laser fusion conceptual designs were used ARIES-AT HAPL
  • 6. Calculation of damage Parameters Rates of dpa, He production, H production, and % burnup calculated for both sublattices of SiC fiber/matrix and interface material The cross section library includes all partial reaction cross sections required to determine gas production and transmutations The library includes the damage energy cross sections needed to determine the atomic displacements Used recommended displacement energies for SiC, namely 20 and 40 eV for the C and Si sublattices, respectively Leading interface material candidates are graphite and multilayer SiC Damage parameters for the SiC interface material are identical to those for the SiC fiber/matrix Damage parameters for the graphite interface material are same as those for C sublattice of SiC except for dpa due to the higher (30 eV) displacement energy M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna
  • 7. Peak Damage Parameters in OB SiC/SiC FW of MFE System M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Flibe Blanket LiPb Blanket
  • 8. Observations on Peak Damage Parameters in MFE System dpa rates in C and Si sublattices of the SiC fiber/matrix are comparable dpa rate in graphite interface is 33% lower than in C sublattice of SiC He production rate in C sublattice of SiC and graphite interface is about a factor of 4 higher than in Si sublattice of SiC and is dominated by the (n,n´3 ) reaction He production rate in graphite interface is 60% higher than average He production rate in the SiC fiber/matrix Significant hydrogen production occurs in Si with a negligible amount produced in C Burnup rate of Si sublattice is twice that for C sublattice of SiC fiber/matrix and graphite interface M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna
  • 9. Comments on Burnup of SiC Burnup of Si sublattice is about a factor of 2 more than that for C sublattice The burnup is equivalent to introducing impurities in the sublattices of the SiC Property degradation depends on the kind of impurities introduced Transmutation of Si produces primarily Mg and Al with smaller amount of P and main transmutation product for C is Be with smaller amount of B and Li Nonstoichiometric burnup of Si and C is expected to be worse than stoichiometric burnups and could be an important issue for SiC M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna
  • 10. Impact of Breeder/Coolant on SiC/SiC Damage Parameters 10-3 10-2 10-1 100 101 102 103 104 0 10 20 30 40 50 60 70 80 dpa/FPY in PbLi blanket He appm/FPY in PbLi blanket dpa/FPY in Flibe blanket He appm/FPY in Flibe blanket DamageRateinSiC Depth in Blanket (cm) Outboard in MFE Reactor Neutron Wall Loading 6 MW/m 2 M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Peak dpa values with Flibe are about half those with LiPb Peak gas production and burnup rates with Flibe are higher by 3-10% than with LiPb dpa values with Flibe have steeper radial drop compared to that in LiPb blanket while gas production and burnup rates have slightly less steep radial drop Flibe is more effective attenuating intermediate energy neutrons while LiPb is more effective attenuating high-energy neutrons
  • 11. Neutron Energy Spectra at FW for LiPb and Flibe Blankets M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Harder spectrum with Flibe Larger total neutron flux with LiPb due to increased secondary neutron production from Pb that are mostly in the 10 keV to 2 MeV range These intermediate energy neutrons result in higher dpa with LiPb High energy flux (E>2 MeV) is much smaller with LiPb resulting in lower gas production and burnup rates 10 4 10 6 10 8 10 10 10 12 10 14 10 -2 10 0 10 2 10 4 10 6 10 8 PbLi Blanket Flibe Blanket NeutronFluxperEnergyGroup(n/cm 2 s) Neutron Energy (eV) Energy spectrum at first wall OB in MFE reactor 6 MW/m 2 neutron wall loading 175 Energy Groups
  • 12. Different Features of IFE Systems M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Significant geometrical, spectral and temporal differences between IFE and MFE systems affect radiation damage levels with impact on lifetime assessment Geometrical differences: Point source in IFE Source neutrons in IFE chambers impinge on the FW/blanket in a perpendicular direction For same NWL, lower radiation effects at FW with smaller radial gradient in blanket Point source at target FW FW Volumetric source in plasma IFE Chamber MFE Chamber
  • 13. Different Features of IFE Systems M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Energy Spectrum for Neutrons Emitted from HAPL Target Combined geometrical and spectral differences impact time-integrated radiation damage parameters Simple scaling of radiation effects with neutron wall loading between IFE and MFE systems is inappropriate Spectral differences: • Fusion neutron interactions in compressed IFE target result in considerable softening of neutron spectrum incident on the FW/ blanket in IFE chambers • Softened source neutron spectrum with 10-13 MeV average energy depending on target R with some neutron multiplication (~1.05)
  • 14. Peak Damage Parameters in SiC/SiC FW of HAPL M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Flibe Blanket LiPb Blanket
  • 15. Comparison between FW Neutron Spectra in IFE and MFE Calculated total neutron flux values at FW are nearly identical in both systems for the same NWL Spectrum is softer in IFE system with average energy of 1.66 MeV compared to 2.67 MeV in MFE system M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna 10 4 10 6 10 8 10 10 10 12 10 14 10 -2 10 0 10 2 10 4 10 6 10 8 IFE OB in MFE NeutronFluxperEnergyGroup(n/cm 2 s) Neutron Energy (eV) Energy spectrum at first wall PbLi blanket 6 MW/m 2 neutron wall loading 175 Energy Groups 10 10 10 11 10 12 10 13 10 14 10 15 10 6 10 7 IFE OB in MFE NeutronFluxperEnergyGroup(n/cm 2 s) Neutron Energy (eV) Energy spectrum at first wall PbLi blanket 6 MW/m 2 neutron wall loading 175 Energy Groups
  • 16. Comparison between FW Damage Parameters in IFE and MFE • Peak values for the same neutron wall loading are significantly different • Gas production and burnup rates are about a factor of 2 lower in IFE system compared to that in MFE system with the same NWL • The peak dpa rate in IFE is lower than that in the OB region of MFE by ~7% for LiPb blanket and ~20% for Flibe blanket • These differences are due to geometrical and spectral differences between IFE and MFE systems M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna
  • 17. Pulsed Effects in IFE Systems M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna In IFE chamber neutron source has a pulsed nature Energy spectrum of neutrons from target results in time of flight spread and backscattering from blanket extends period over which a particular radiation effect takes place Time spread is larger for radiation effects produced by lower energy neutrons (time spread of dpa larger than that for gas production and transmutation)
  • 18. Pulsed Effects in IFE Systems (Cont’d) M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Peak instantaneous damage rates in IFE FW/blanket are ~5 to 8 orders of magnitude higher than steady state damage rates produced in MFE systems Difference in time spread results in higher instantaneous He/dpa ratios in IFE systems compared to MFE systems Time dependent neutronics analysis is necessary for subsequent microstructure evolution analysis Analysis is underway to determine pulsed instantaneous damage parameters in SiC/SiC FW of HAPL and couple results with microstructure evolution analysis
  • 19. Pulsed Damage parameters in HAPL SiC/SiC FW M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Temporal peaking factor is significantly higher for He production than for atomic displacement (8.7x107 vs. 1.1x107) Peak instantaneous He/dpa ratio is much higher than that determined from the temporal average (cumulative) values (368 vs. 47)
  • 20. Use of SiC FCI as Insulator in DCLL Blanket • The Dual Coolant Lithium Lead (DCLL) blanket concept is the preferred US blanket concept for commercial fusion plants • It provides a pathway to high outlet temperature with current generation structural materials • A key element is use of SiC (foam or composite) flow channel inserts (FCI) for electrical and thermal insulation M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna
  • 21. Peak Damage Parameters in SiC FCI of DCLL Blanket Neutronics calculations for the DCLL concept in OB region of MFE system with a NWL of 6 MW/m2 M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna Relative values for different constituents are similar to those obtained for the SiC/SiC FW of self-cooled LiPb blanket Damage parameter values are lower by ~40% due to attenuation in the 3 cm thick He-cooled ferritic steel FW
  • 22. Metallic Transmutation Products in SiC FCI M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna FCI is not a structural element and main concern is degradation in its primary role as electrical and thermal insulator Degradation in resistivity results from introduction of metallic transmutation products Transmutation calculations using the ALARA code determined rate of build-up of different metallic transmutation products 00 1000 2000 3000 4000 5000 0 0.5 1 1.5 2 2.5 3 3.5 Li Be B Mg Al P TTransmutationProduction(appm) Operation Time (FPY) 6 MW/m 2 Neutron Wall Loading Front Layer of SiC FCI in DCLL Blanket Dominant metallic transmutation product is Mg that builds up to ~0.43 at% concentration at the expected lifetime of a DCLL blanket in a fusion power plant It is essential to assess impact of these levels on electrical and thermal conductivities of FCI to determine if it will restrict lifetime of the DCLL to less than that determined by radiation damage to ferritic steel FW
  • 23. Conclusions • Radiation damage parameters in SiC/ SiC composite have strong dependence on the blanket design (coolant, breeder) and plasma confinement approach (MFE, IFE) • Input needed from materials community regarding appropriate lifetime criterion M. Sawan 1st RCM on “Nuclear Data Libraries for Advanced Systems- Fusion Devices” 2-5 Dec 2008, IAEA, Vienna