NSUF 15-585: Nanohardness Measurements on Neutron Irradiated Steel Samples for Next Generation Reactors3
This proposal centers on collecting nanohardness data on neutron irradiated steels at UC Berkeley’s radiological laboratory. Neutron irradiated material mechanical testing is critical for the design of next generation reactors and potential accident tolerant improvements to existing reactors. The ATR-NSUF UCSB irradiation has created over 1000 8mm diameter disc multipurpose coupons (DMC) of cladding materials irradiated at a variety of dose and temperature conditions. Materials irradiated at similar and higher doses are also available from the STIP irradiations at the SINQ accelerator at Paul Scherrer Institut. Currently Los Alamos National Laboratory (with UC Santa Barbara) is developing a shear punch apparatus to both gather shear test (shear stress vs elongation) data and to use the punched out region to create smaller 1-2mm diameter sub size samples for future testing. These punched out samples are the perfect size to send to smaller scale radiological labs, such as UC Berkeley’s. These punched samples can be polished in their radiological facility and placed on their nanohardness tester to generate nanohardness data. This nanohardness data, plus the shear punch data collected on the parent material feed into constitutive behavior models for irradiated structural materials. We have proven the viability of collecting nanohardness data from ATR irradiated steels already, via a test of a small number of samples shipped from LANL to UC Berkeley. Now we wish to continue measuring with more samples from the ATR. We propose to send 10-20 samples irradiated at approximately 6-20 dpa at irradiation temperatures ranging from 300-450C from LANL to UCB for polishing and nanohardness measurements. These samples will range from Ferritic/Martensitic steels at various chromium content (HT9, T91, EP823) to a variety of established and newer ODS steels such as MA956, 14YWT and MA957. Nanohardness and microstructural data collected at UCB via this proposal will be correlated with macroscopic shear punch and tensile data from LANL to feed into future constitutive modeling efforts.
Papildoma informacija
| Laukas | Reikšmė |
|---|---|
| Awarded Institution | Los Alamos National Laboratory |
| Embargo End Date | 2026-02-27 |
| Facility Tech Lead | Peter Hosemann |
| NSUF Call | FY 2015 RTE 3rd Call |
| PI | Tarik Saleh |
| Project Member | Dr. Stuart Maloy, Senior Nuclear Materials Adviser - Pacific Northwest National Laboratory (https://orcid.org/0000-0001-8037-1319) |
| Project Member | Professor Peter Hosemann, Professor, - University of California-Berkeley (https://orcid.org/0000-0003-2281-2213) |
| Project Member | Dr. Tarik Saleh, Scientist - Los Alamos National Laboratory (https://orcid.org/0000-0003-2108-4293) |
| Project Type | RTE |
| Publication | Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ˜295 °C to ˜6.5 dpa Stuart Maloy, G. Robert Odette, Tarik Saleh, Takuya Yamamoto, Osman Anderoglu, James Cole Journal of Nuclear Materials 468 2016-01-01 http://www.sciencedirect.com/science/article/pii/S0022311515301264 |
| RTE Number | 585 |