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)

October 8, 2018CFA 16-10393 Review

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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



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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



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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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Results From AM NEET Program

https://www.osti.gov/servlets/purl/1431212


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https://www.osti.gov/servlets/purl/1431212

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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What’s Next?

14GEH Nuclear Energy: Additive

Manufacturing6/7/2017October 8, 2018

CFA 16-10393 Review14

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


Questions?

16GEH Nuclear Energy: Additive

Manufacturing6/7/2017October 8, 2018

CFA 16-10393 Review16

nsuf review board irradiation testing of lwr additively ......nsuf review board irradiation testing...

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