NSUF 08-139: Characterization of the Microstructures and Mechanical Properties of Advanced Structural Alloys for Radiation Service: A Comprehensive Library of ATR Irradiated Alloys and Specimen
Building on four decades of capsule design, neutron irradiation and scientific-based post irradiation examination experience, the Materials Reliability and Performance Group at the University of California, Santa Barbara, and a team of world class collaborators, propose an extensive neutron irradiation program that would utilize the entire length of one of the A positions in the ATR user facility to develop a large library of irradiated structural materials at temperatures from 300 to 800°C and doses of 3-4 dpa. Multiple specimen types, ranging from disc multipurpose coupons to tensile specimens to deformation and fracture specimens, will provide a wide range of post-irradiation examination opportunities to assess microstructural and mechanical property changes, including fracture toughness. The irradiation program also makes use of innovative approaches to studying the strength and toughness of coatings and bonded joints, in addition to diffusion multiple systems that can provide insight into radiation modified inter-diffusion, phase formation processes and phase diagrams over a wide range of irradiation temperatures. The alloys included in the program will largely consist of ferritic steels, advanced nanostructured ferritic alloys and model alloys, as part of DOE-sponsored fusion materials and advanced fission energy programs. The post-irradiation examination, including a wide range of microstructural and mechanical property characterization will primarily be performed at national laboratory hot cells at INL, PNNL, LANL and ORNL funded by various base programs. It is anticipated that the proposed program will eventually involve many university students and post-doctoral researchers and will address scientific questions ranging from from microstructural evolution and phase stability, to radiation hardening and high-temperature radiation softening and non-hardening embrittlement. The impact leveraging and cost effectiveness of the proposed research is without any match.
Thông tin khác
| Miền | Giá trị |
|---|---|
| Awarded Institution | University of California-Santa Barbara |
| Embargo End Date | 2026-02-27 |
| Facility Tech Lead | Alina Montrose, Kory Linton, Stuart Maloy |
| NSUF Call | FY 2008 Call for User Proposals |
| PI | Takuya Yamamoto |
| Project Member | Dr. Brian Wirth - University of Tennessee-Knoxville |
| Project Member | Dr. Takuya Yamamoto, Professional Research - University of California-Santa Barbara (https://orcid.org/0000-0002-6480-5225) |
| Project Member | Jeremy Busby - Oak Ridge National Laboratory |
| Project Member | Dr. Stuart Maloy, Senior Nuclear Materials Adviser - Pacific Northwest National Laboratory (https://orcid.org/0000-0001-8037-1319) |
| Project Member | Professor G. Robert Odette - University of California-Santa Barbara (https://orcid.org/0000-0002-7700-9391) |
| Project Member | Mychailo Toloczko, Scientist - Pacific Northwest National Laboratory (https://orcid.org/0000-0003-3878-6101) |
| Project Type | Irradiation/PIE |
| Publication | Microstructural changes in a neutron-irradiated Fe–15 at.%Cr alloy Mukesh Bachhav, Emmanuelle Marquis, G. Robert Odette Journal of Nuclear Materials 454 2014-11-01 http://www.sciencedirect.com/science/article/pii/S0022311514005546 |
| Publication | Evolution of manganese–nickel–silicon-dominated phases in highly irradiated reactor pressure vessel steels James Cole, Brandon Miller, Tim Milot, G. Robert Odette, Peter Wells, Takuya Yamamoto Acta Materialia 80 2014-11-03 http://www.sciencedirect.com/science/article/pii/S1359645414005588#ak005 |
| 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 |
| Publication | Mechanical properties and plasticity size effect of Fe-6%Cr irradiated by Fe ions and by neutrons G. Robert Odette, Chris Hardie, Steve Roberts Journal of Nuclear Materials 482 2016-12-15 http://www.sciencedirect.com/science/article/pii/S0022311516309515 |
| Publication | Thermodynamic and kinetic modeling of Mn-Ni-Si precipitates in low-Cu reactor pressure vessel steels Nathan Almirall, Philip Edmondson, G. Robert Odette, Peter Wells, Dane Morgan Acta Materialia 138 2017-10-03 https://www.sciencedirect.com/science/article/pii/S1359645417305712#ack0010 |
| Publication | On the status and prospects for nanostructured ferritic alloys for nuclear fission and fusion application with emphasis on the underlying science G. Robert Odette Scripta Materialia 143 2018-01-01 https://www.sciencedirect.com/science/article/pii/S1359646217303342#ac0005 |
| Publication | Thermodynamics and kinetics of core-shell versus appendage co-precipitation morphologies: An example in the Fe-Cu-Mn-Ni-Si system Shipeng Shu, Peter Wells, Nathan Almirall, G. Robert Odette Acta Materialia 157 2018-09-01 https://www.sciencedirect.com/science/article/pii/S1359645418305652#ack0010 |
| Publication | SOME USEFUL MECHANICAL PROPERTY CORRELATIONS FOR NUCLEAR REACTOR PRESSURE VESSEL STEELS G. Robert Odette, Nathan Almirall ASME 2018 2018-07-15 - 2018-07-20 |
| Publication | The crystal structure, orientation, relationships and interfaces of the nanoscale oxides in nanostructured ferritic alloys Nathan Bailey, G. Robert Odette, Peter Hosemann Acta Materialia 111 2016-06-01 https://www.sciencedirect.com/science/article/pii/S1359645416301847#ack0010 |
| Publication | Compatibility of an FeCrAl alloy with flowing Pb-Li in a thermal convection loop Journal of Nuclear Materials 492 2017-08-01 https://www.sciencedirect.com/science/article/pii/S0022311517306293#ack0010 |
| Publication | Microstructural changes and their effect on hardening in neutron irradiated Fe-Cr alloys Dhriti Bhattacharyya, Takuya Yamamoto, Peter Wells, Emmanuelle Marquis, Mukesh Bachhav, G. Robert Odette Journal of Nuclear Materials 519 2019-06-12 https://www.sciencedirect.com/science/article/pii/S0022311518314119#ack0010 |
| Publication | Precipitation and hardening in irradiated low alloy steels with a wide range of Ni and Mn compositions G. Robert Odette, Nathan Almirall, Peter Wells, Takuya Yamamoto Acta Materialia None 2019-08-18 https://doi.org/10.1016/j.actamat.2019.08.027 |
| Publication | Irradiation-induced Precipitation in Ni-based Superalloys, L-J Yu; G Burke; EA Marquis Emmanuelle Marquis Annual TMS meeting 2019-03-10 - 2019-03-14 |
| Publication | Dose rate effects on the precipitation behavior of Fe-Cr and Ni alloys, E Reese, LJ Yu, T Yamamoto, GR Odette, EA Marquis Emmanuelle Marquis 6th FMTCP workshop 2019-06-24 - 2019-06-26 |
| Publication | Influence of Irradiation Conditions on Precipitation Behavior in Fe-Cr and Ni Alloys Emmanuelle Marquis, Nathan Almirall, Takuya Yamamoto, G. Robert Odette, Grace Burke Annual TMS meeting 2019-03-10 - 2019-03-14 |
| Publication | Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy Jack Haley, G. Robert Odette, Steve Roberts Journal of Nuclear Materials 533 2020-05-01 https://www.sciencedirect.com/science/article/pii/S0022311519312528#ack0010 |
| Publication | Flux effects in precipitation under irradiation – Simulation of Fe-Cr alloys Emmanuelle Marquis, G. Robert Odette Acta Materialia 164 2019-02-01 https://www.sciencedirect.com/science/article/pii/S1359645418308735#ack0010a |
| Publication | A kinetic lattice Monte Carlo study of post-irradiation annealing of model reactor pressure vessel steels G. Robert Odette, Shipeng Shu, Peter Wells, Dane Morgan Journal of Nuclear Materials None 2019-07-18 https://www.sciencedirect.com/science/article/pii/S0022311519301667 |
| Publication | On a' precipitate composition in thermally annealed and neutron-irradiated Fe- 9-18Cr alloys Mukesh Bachhav, Emmanuelle Marquis, G. Robert Odette, Peter Wells, Takuya Yamamoto Journal of Nuclear Materials 500 2018-03-01 https://www.sciencedirect.com/science/article/pii/S0022311517309285 |
| Publication | Recent Progress in Developing and Qualifying Nanostructured Ferritic Alloys for Advanced Fission and Fusion Applications G. Robert Odette JOM 66 2014-11-12 https://link.springer.com/article/10.1007/s11837-014-1207-5 |
| Publication | Structural characterization of nanoscale intermetallic precipitates in highly neutron irradiated reactor pressure vessel steels David Sprouster, Eric Dooryhee, Peter Wells, Nathan Almirall, G. Robert Odette, Lynne Ecker Scripta Materialia 113 2015-10-21 https://www.sciencedirect.com/science/article/pii/S135964621530018X |
| RTE Number | 139 |