The origin of exceptional IASCC resistance of the additively-manufactured stainless steel after hot isostatic pressing
- Name:
- Xiaoyuan Lou
- Email:
- [email protected]
- Phone:
- 334-844-5071
| Name: | Institution: | Expertise: | Status: |
|---|---|---|---|
| Randy Nanstad | |||
| Miao Song | University of Michigan | Proton irradiation and TEM | Other |
| Raul Rebak | GE Research | additive manufacturing, IASCC | Other |
- Experiment Title:
- The origin of exceptional IASCC resistance of the additively-manufactured stainless steel after hot isostatic pressing)
- Work Description:
- The experimental design serves two purposes: (1) validating the IASCC improvement through different heats of materials and post-heat treatments; (2) confirming the mechanistic hypothesis. Auburn University will provide two heats of AM 316L SS to be studied in this project. The materials will be fabricated with different laser processing conditions using laser powder bed fusion. The study will focus on the effects of two kinds of post-treatments: (1) solution annealing only; (2) HIP + solution annealing. Both treatments will be done at Auburn University. Auburn University will be responsible for machining to required mini tensile bar geometry. With one repeat for each testing condition, the total 8 mini tensile bars need to be irradiated. UM has extensive IASCC data for wrought 316L to compare, so no wrought materials will be tested in the study. The proton irradiation with 2 MeV protons will be conducted in the Michigan Ion Beam Laboratory (MIBL). Irradiations were performed at a temperature of 360 ⁰C with the dose level to 2.5 dpa. 6 TEM bars (both wrought and AM materials) will also be irradiated with those tensile bars at the same time. After the radiation, the tensile bars will be shipped back to Auburn University for the SSRT test. The SSRT test will be conducted in Boiling Water Reactor (BWR) environment at 288 ⁰C and 2 ppm dissolved oxygen. A strain rate of 1x10-7 s-1 was applied until a plastic strain of 4% was reached. TEM characterization time at CAES is also requested by this project to compare grain boundary elemental segregation before and after proton irradiation. 8 days of irradiation time at UM and 2 days of TEM characterization time at CAES are requested by this proposal to complete this study.
"Dislocation channel broadening–A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless steel" Xiaoyuan Lou, Acta Materialia 266 2024 119650
"A comparison study of void swelling in additively manufactured and cold-worked 316L stainless steels under ion irradiation" Xiaoyuan Lou, Journal of Nuclear Materials 551 2021 152946
"Compositionally graded specimen made by laser additive manufacturing as a high-throughput method to study radiation damages and irradiation-assisted stress corrosion cracking" Xiaoyuan Lou, Journal of Nuclear Materials 560 2022 153493 Link
"Intragranular irradiation-assisted stress corrosion cracking (IASCC) of 316L stainless steel made by laser direct energy deposition additive manufacturing: Delta ferrite-dislocation channel interaction" Xiaoyuan Lou, Journal of Nuclear Materials 577 2023 154305 Link
"Void swelling in additively manufactured 316L stainless steel with Hafnium composition gradient under self-ion irradiation" Xiaoyuan Lou, Journal of Nuclear Materials 578 2023 154351 Link
About Us
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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