054-2010-123

Advanced Damage Tolerant Ceramics: Candidates for Nuclear Structural Applications

NFML Details
Program
NSUF
Project
Advanced Damage Tolerant Ceramics: Candidates for Nuclear Structural Applications
Reactor
ATR
Reactor Position
EFT 5
Sample Id Code
054-2010-123
Capsule
DxU-J
Packet
N/A
Material Code
SiC (G1)
Material Name
Silicon carbide (SiC)
Material Description
MAX Alloy
Material Tags
Ceramic, Carbide, Carborundum, Cladding, Semiconductor, Cubic phase
KGT Num
1379
Specimen Type
TEM
Dimensions (mm)
7 x 5.3 with 1 mm gauge
Number Of Samples
5
Samples Remaining
No Samples Remaining Defined
Date Added
No Date Added Defined
Available for Research
Yes
Anticipated Availability
November 26, 2014
Storage Facility
Hot Fuel Examination Facility
Notes
As-run temp from ECAR-3034 pD1, As-Run DPA avg ECAR-3028 p68
Planned Temp (°C)
100.00
Planned Dose (DPA)
9
Planned Fluence (n/cm²)
No planned Fluence Value Defined
Planned Flux (n/cm²/s)
No planned Flux Value Defined
Planned Environment
Helium/Argon
As Run Total Dose (DPA)
4.74
As Run Total Fluence (n/cm²)
1.73E+22
Composition by Wt. (%)
Si -36.46C
Cycles (4)