Status of Post Irradiation Examination of FCAB and FCAT Irradiation Capsules

Technical Report · Thu Sep 29 00:00:00 EDT 2016

DOI:https://doi.org/10.2172/1328331· OSTI ID:1328331

Field, Kevin G. ^[1]; Yamamoto, Yukinori ^[1]; Howard, Richard H. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Fuel Cycle Research and Development (FCRD)

A series of irradiation programs are ongoing to address the need for determining the radiation tolerance of FeCrAl alloys. These irradiation programs, deemed the FCAT and FCAB irradiation programs, use the High Flux Isotope Reactor (HFIR) to irradiate second generation wrought FeCrAl alloys and early-generation powder-metallurgy (PM) oxide dispersion-strengthened (ODS) FeCrAl alloys. Irradiations have been or are being performed at temperatures of 200°C, 330°C, and 550°C from doses of 1.8 dpa up to 16 dpa. Preliminary post-irradiation examination (PIE) on low dose (<2 dpa) irradiation capsules of tensile specimens has been performed. Analysis of co-irradiated SiC thermometry have shown reasonable matching between the nominal irradiation temperatures and the target irradiation temperatures. Room temperature tensile tests have shown typical radiation-induced hardening and embrittlement at irradiations of 200°C and 330°C, but a propensity for softening when irradiated to 550°C for the wrought alloys. The PM-ODS FeCrAl specimens showed less hardening compared to the wrought alloys. Future PIE includes high temperature tensile tests on the low dose irradiation capsules as well as the determination of reference fracture toughness transition temperature, T_o, in alloys irradiated to 7 dpa and higher.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5). Advanced Fuel Campaign; USDOE Office of Science (SC), Basic Energy Sciences (BES)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1328331
• Report Number(s): ORNL/TM-2016/558; AF5810000; NEAF278; TRN: US1700346
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
LOW DOSE IRRADIATION
IRRADIATION CAPSULES
RADIATION HARDENING
OXIDES
IRON BASE ALLOYS
CHROMIUM ALLOYS
ALUMINIUM ALLOYS
TERNARY ALLOY SYSTEMS
POST-IRRADIATION EXAMINATION
TRANSITION TEMPERATURE
TEMPERATURE RANGE 0400-1000 K
RADIATION DOSES
COMPARATIVE EVALUATIONS
FRACTURE PROPERTIES
POWDER METALLURGY
DISPERSIONS
EMBRITTLEMENT