Nuclear damage Parameters for SiC/SiC Composite in Fusion Systems
[Pages:23]Nuclear dam age Param et ers for SiC/ SiC Com posit e in Fusion Syst em s
Moham ed Sawan
Fusion Technology I nst it ut e The Universit y of Wisconsin- Madison
Yut ai Kat oh, Lance Snead
Mat erials Science and Technology Division Oak Ridge nat ional Laborat ory
I nt ernat ional Sym posium on Silicon Carbide and Carbon- Based Mat erials for Fusion and Advanced Nuclear Energy applicat ions
January 19- 22, 2009 Dayt ona Beach, FL
Much Harder Neut ron Spect rum in Fusion Com pared t o Fission
1015
Fusion 14.1 MeV Peak
Neutron Flux per Group (n/cm2s)
Fusion Lacks Significant Therm al Com ponent
1013 1011 109 107
Average Energy Fission 0.7 MeV Fusion 2.7 MeV
Fission Reactor Fusion Reactor FW
Neutron spectra normalized to 1015 n/cm2s total flux
46 Energy Group Structure
1015 0-2
100
102
104
106
108
Neutron Energy (eV)
He/ dpa rat io is significant ly higher t han in a fission react or nuclear environm ent ( ~ 10 vs. ~ 0.3 for FS)
Effect m ore pronounced for SiC ( ~ 90 vs. ~ 1 for SiC)
M. Sawan
1st RCM on " Nuclear Dat a Libraries for Advanced Syst em s- Fusion Devices" 2- 5 Dec 2008, I AEA, Vienna
Applicat ion of SiC/ SiC Com posit es in Fusion Syst em s
SiC/ SiC com posit es have been considered for use in fusion syst em s
Because of t heir low induced radioact ivit y and high t em perat ure operation they represent an attractive candidate for structural m aterial
They have been proposed as st ruct ural m at erial for FW and blanket in several MFE and I FE designs
SiC/ SiC com posit e is t he preferred st ruct ural m at erial for FW and blanket of t he HAPL I FE design wit h m agnet ic int ervent ion
SiC/ SiC com posit es are considered for use as flow channel insert s ( FCI ) in dual coolant lit hium lead blanket ( DCLL) . They provide elect rical insulat ion t o m it igat e MHD effect s and t herm ally isolat e t he high t em perat ure LiPb from t he low t em perat ure helium cooled FS
Lifet im e of SiC/ SiC com posit es in fusion radiat ion environm ent is a m aj or critical issue
Radiat ion effect s in fiber, m at rix, and int erface com ponent s represent im portant input for lifetim e assessm ent
I m pact of radiat ion on insulat ing propert ies of FCI is also a crit ical issue
M. Sawan
1st RCM on " Nuclear Dat a Libraries for Advanced Syst em s- Fusion Devices" 2- 5 Dec 2008, I AEA, Vienna
High Average power Laser ( HAPL) Concept ual Design
Dry wall m ust accom m odat e ion and photon threat spectra from target
Ext rem e flux of int erm ediat e energy ions pose a significant issue of
extrem ely high pulsed tem peratures
and erosion/ ablat ion of FW
Magnet ic int ervent ion used t o st eer ions away from cham ber wall
? Direct drive targets
? Dry wall cham ber ? 40 KrF laser beam s
? 367.1 MJ t arget yield ? 5 Hz Rep Rat e ? 6 MW/ m 2 peak NWL
Large fract ion of m agnet ic energy can be dissipated in cham ber walls if an electrically resistive structural m aterial is used ( SiC/ SiC)
LiPb or Flibe self- cooled blanket s used
1 cm Be insert used in FW coolant channel wit h Flibe for t rit ium selfsufficiency
M. Sawan
1st RCM on " Nuclear Dat a Libraries for Advanced Syst em s- Fusion Devices" 2- 5 Dec 2008, I AEA, Vienna
Nuclear Analysis for SiC/ SiC in
Fusion Environm ent
Radiat ion param et ers det erm ined for SiC/ SiC com posit es for MFE and I FE syst em s
Configurat ions of ARI ES-AT advanced t okam ak and HAPL laser fusion conceptual designs were used
M. Sawan
ARI ES- AT
HAPL
1st RCM on " Nuclear Dat a Libraries for Advanced Syst em s- Fusion Devices" 2- 5 Dec 2008, I AEA, Vienna
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