NSUF - Nuclear Science User Facilities

Characterization of the Microstructures and Mechanical Properties of Advanced Structural Alloys for Radiation Service: A Comprehensive Library of ATR Irradiated Alloys and Specimen

Full Details
Principal Investigator
Name:
Takuya Yamamoto
Email:
[email protected]
Phone:
(208) 526-6918
Team Members:
Name: Institution: Expertise: Status:
Brian Wirth University of California - Berkeley
Jeremy Busby Oak Ridge National Laboratory
Stuart Maloy Los Alamos National Laboratory
Mychailo Toloczko Pacific Northwest National Laboratory
G. Robert Odette University of California - Santa Barbara
Richard Kurtz Pacific Northwest National Laboratory
Takuya Yamamoto University of California - Santa Barbara
Experiment Details:
Experiment Title:
Characterization of the Microstructures and Mechanical Properties of Advanced Structural Alloys for Radiation Service: A Comprehensive Library of ATR Irradiated Alloys and Specimen)
Project Summary
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.
Book / Journal Publications

"Microstructural changes in a neutron-irradiated Fe–15 at.%Cr alloy" Mukesh Bachhav, Emmanuelle Marquis, G. Robert Odette, Journal of Nuclear Materials 454 2014 381-386 Link

"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, Yuan Wu, Acta Materialia 80 2014 205-219 Link

"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, T. J. Romero, Shuangchen Li, James Cole, Randall Fielding, Journal of Nuclear Materials 468 2016 232-239 Link

"Mechanical properties and plasticity size effect of Fe-6%Cr irradiated by Fe ions and by neutrons" G. Robert Odette, Chris Hardie, Shavkat Akhmadaliev, Steve Roberts, Y Wu, Journal of Nuclear Materials 482 2016 236-247 Link

"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, Huibin Ke, Leland Barnard, Dane Morgan, Acta Materialia 138 2017 10-26 Link

"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 142-148 Link

"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, DD Morgan, Acta Materialia 157 2018 298-306 Link

"The crystal structure, orientation, relationships and interfaces of the nanoscale oxides in nanostructured ferritic alloys" Yuan Wu, Jim Criston, Stephan Kraemer, Nathan Bailey, G. Robert Odette, Peter Hosemann, Acta Materialia 111 2016 108-115 Link

"Compatibility of an FeCrAl alloy with flowing Pb-Li in a thermal convection loop" Steven Pawel, Kinga Unocic, Journal of Nuclear Materials 492 2017 41-51 Link

"Microstructural changes and their effect on hardening in neutron irradiated Fe-Cr alloys" Dhriti Bhattacharyya, Takuya Yamamoto, Peter Wells, Emmanuelle Marquis, Mukesh Bachhav, Yuan Wu , Joel Davis, Alan Xu, G. Robert Odette, Journal of Nuclear Materials 519 2019 274-286 Link

"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 2019 119-128 Link

"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 Link

"Flux effects in precipitation under irradiation – Simulation of Fe-Cr alloys" JH Ke, ER Reese, Emmanuelle Marquis, G. Robert Odette, DD Morgan, Acta Materialia 164 2019 586-601 Link

"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 2019 312-322 Link

"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, Elaina Reese, Journal of Nuclear Materials 500 2018 192-198 Link

"Recent Progress in Developing and Qualifying Nanostructured Ferritic Alloys for Advanced Fission and Fusion Applications" G. Robert Odette, JOM 66 2014 2427-2441 Link

"Structural characterization of nanoscale intermetallic precipitates in highly neutron irradiated reactor pressure vessel steels" DAVID SPROUSTER, Eric Dooryhee, John Sinsheimer, Sanjit Ghose, Peter Wells, Nathan Almirall, G. Robert Odette, Lynne Ecker, Tiberiu Stan, Scripta Materialia 113 2015 18-22 Link

Conference Publications

"SOME USEFUL MECHANICAL PROPERTY CORRELATIONS FOR NUCLEAR REACTOR PRESSURE VESSEL STEELS" Randy Nanstad, G. Robert Odette, William Server, Mikhail Sokolov, Nathan Almirall, ASME 2018 July 15-20, (2018)

"Irradiation-induced Precipitation in Ni-based Superalloys, L-J Yu; G Burke; EA Marquis" Emmanuelle Marquis, Annual TMS meeting March 10-14, (2019)

"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 June 24-26, (2019)

"Influence of Irradiation Conditions on Precipitation Behavior in Fe-Cr and Ni Alloys" Emmanuelle Marquis, E Reese, LJ Yu, Nathan Almirall, Takuya Yamamoto, G. Robert Odette, Grace Burke, Annual TMS meeting March 10-14, (2019)

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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