NSUF Review Board Irradiation Testing of LWR Additively ......NSUF Review Board Irradiation Testing...
Transcript of NSUF Review Board Irradiation Testing of LWR Additively ......NSUF Review Board Irradiation Testing...
NSUF Review Board Irradiation Testing of LWR Additively Manufactured Material
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Fran Bolger
October 8, 2018
DOE Program - CFA-16-10393Irradiation Testing of LWR Additively Manufactured Materials• Objective: Perform full irradiation / PIE on structural
materials produced by DMLM
• Participants: GEH (Connor - PI), INL (NSUF facility)
• Activities: Obtain microstructural characterization, mechanical properties, stress corrosion crack growth data for un-irradiated Type 316L and IN 718 (GEH) and corresponding irradiated data to ~0.7 dpa (INL at the ATR)
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CFA-16-10393 Project
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Timeline
Fabrication and Unirradiated Testing (GEH)
• Fabricate 316L and IN718 samples
• Mechanical Testing (tensile, toughness, fatigue, SCC)
ATR Irradiation (INL)
• SCC testing for unirradiated IN718
• Irradiation –4 cycles starting in August, 2017
• Complete Nov, 2018
PIE (INL)
• Initiate in Dec, 2018
• IASCC, Fracture Toughness, Tensile, TEM
2016-2017 2017-2019 2019
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Value and Challenges of Additive
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Powder Bed Laser Fusion Process
• Additive Manufacturing provides many advantages:• Speeds up Innovation• Design-driven manufacturing as opposed to
manufacturing-constrained design• Specialized materials
• Nuclear industry has more difficulty in incorporating new materials, designs• Costly validation, limited facilities
• Collaboration between NSUF and GEH will facilitate more rapid use of Additive Manufacturing
GEH Proprietary Information – Class II (Internal)
316L DMLM Material Properties
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Mechanical Properties
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Tensile Testing: Yield Stress
0.05.0
10.015.020.025.030.035.040.045.0
0.2%
(K
SI)
ROOM TEMPERATURE 0.0
5.0
10.0
15.0
20.0
25.0
0.2%
(K
SI)
OPERATING TEMPERATURE 550F
Wrought 316L
AM 316L
AM 316L
Mechanical Properties
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Tensile Testing: Elongation and Reduction of Area
0.010.020.030.040.050.060.070.080.090.0
100.0
ELO
NG
ATIO
N (%
)
ROOM TEMPERATURE0.0
10.020.030.040.050.060.070.080.090.0
100.0
RE
DU
CTI
ON
OF
AR
EA
(%)
ROOM TEMPERATURE
Wrought 316L
AM 316L
AM 316L
Mechanical Properties
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Fatigue Test for AM 316L
1
10
100
1000
1E+0 1E+1 1E+2 1E+3 1E+4 1E+5 1E+6 1E+7 1E+8 1E+9 1E+10 1E+11
Stre
ss A
mpl
itude
(Ksi)
# of Cycles to Failure
Design Fatigue Curves for Austenitic Steels, Ni-Cr-Fe Alloy andNi-Cu Alloy for Temperatures Under 425°C (800F)
Design Limit 316L (H&V combined) Machined 316L (H&V combined) As-Built
Fatigue Performance meets design limits.Machining and Surface Treatment Improve Life.
316L CGR in NWC and HWC conditions (performed by GE)
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IN718 CGR in NWC and HWC conditions
(performed by INL)
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GEH Proprietary Information – Class II (Internal)
Results From AM NEET Program
https://www.osti.gov/servlets/purl/1431212
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Experiment
Parameter 2 MeV Proton 5 MeV Fe++(QCAM316L
only)Dose (dpa) 5 100
Temperature (○C) 360 400
Damage rate (dpa/s) 1.6 × 10-5 3.6 × 10-4
Current (𝜇𝜇A) 37 0.618
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Irradiation stage
• Irradiation
• Constant Extension Rate Tensile (CERT) test in BWR (NWC) environment– 288°C, 2000 ppb [O2]– Slow strain rate: ~ 1 × 10-7 s-1
– Plastic deformation: ~ 4 %
Cracking susceptibility of GE materials
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GEH Proprietary Information – Class II (Internal)
What’s Next?
14GEH Nuclear Energy: Additive
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NRC and Material Licensing
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• NRC has become active in the consideration of AM for nuclear with workshops, visits, and vendor discussions
• EPRI is doing some 316L AM development and testing work and is planning to submit an ASME code case
• GEH would like to obtain BWRVIP-84 review for AM material (future DOE proposal)
• It would be useful to connect the NSUF neutron test results with the proton and ion results
GEH Proprietary Information – Class II (Internal)
Questions?
16GEH Nuclear Energy: Additive
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