NSUF 12-355: Post Irradiation Tensile Performance of Fe-Cr Base Alloys

Post Irradiation Tensile Performance of Fe-Cr Base Alloys This proposal describes the use of x-ray diffraction experiments at the Advanced Photon Source to study the evolution of tensile properties of ferritic alloys following irradiation at the ATR. The samples consist of a selection of model, commercial, and developmental FeCr alloys, the primary choice for reactor fuel cladding and structural applications in advanced reactor designs. The samples are in minitensile form, presently undergoing irradiation inside the ATR. Once removed from the ATR the samples will be loaded into interchangeable tensile testing jaws and placed inside a sealed glovebox containing the tesile testing stage. The specially constructed glovebox will allow the tensile stage to be mounted on the MRCAT beamline, maintaining the appropriate geometry for x-ray diffraction, as well providing containment for the irradiated samples. The measurements will utilize a two-dimensional area detector to record the diffraction pattern. This will allow bulk stress and strain components to be measured in situ during the tensile tests, as well as monitoring the development of plasticity-induced voids which lead to flow localization (necking). Diffraction data will be available for analysis as it is collected, and the full data set available for analysis immediately after the conclusion of the beamtime. The period of performance is therefore limited to the constraints of the sample irradiation and beamtime award schedule, with additional time required only for the analysis of experimental data. With a favorable outcome, these experiments could be extended to further radiation doses or other systems of interest. If successful, these studies will complement information obtained from higher dose irradiations in the Phenix fast reactor. These experiments will extend current experimental and modeling activities, including the use of the viscoplastic selfconsistent (VPSC) polycrystal approach to understanding the tensile behavior of alloy systems as a function of irradiation dose, as well as finite element analysis of deformation and structural loads. Ultimately, this will improve our understanding of the deformation mechanisms of critical importance to performance and lifetime prediction of the next generation of nuclear reactor components.

Additional Info

Field	Value
Abstract	Post Irradiation Tensile Performance of Fe-Cr Base Alloys This proposal describes the use of x-ray diffraction experiments at the Advanced Photon Source to study the evolution of tensile properties of ferritic alloys following irradiation at the ATR. The samples consist of a selection of model, commercial, and developmental FeCr alloys, the primary choice for reactor fuel cladding and structural applications in advanced reactor designs. The samples are in minitensile form, presently undergoing irradiation inside the ATR. Once removed from the ATR the samples will be loaded into interchangeable tensile testing jaws and placed inside a sealed glovebox containing the tesile testing stage. The specially constructed glovebox will allow the tensile stage to be mounted on the MRCAT beamline, maintaining the appropriate geometry for x-ray diffraction, as well providing containment for the irradiated samples. The measurements will utilize a two-dimensional area detector to record the diffraction pattern. This will allow bulk stress and strain components to be measured in situ during the tensile tests, as well as monitoring the development of plasticity-induced voids which lead to flow localization (necking). Diffraction data will be available for analysis as it is collected, and the full data set available for analysis immediately after the conclusion of the beamtime. The period of performance is therefore limited to the constraints of the sample irradiation and beamtime award schedule, with additional time required only for the analysis of experimental data. With a favorable outcome, these experiments could be extended to further radiation doses or other systems of interest. If successful, these studies will complement information obtained from higher dose irradiations in the Phenix fast reactor. These experiments will extend current experimental and modeling activities, including the use of the viscoplastic selfconsistent (VPSC) polycrystal approach to understanding the tensile behavior of alloy systems as a function of irradiation dose, as well as finite element analysis of deformation and structural loads. Ultimately, this will improve our understanding of the deformation mechanisms of critical importance to performance and lifetime prediction of the next generation of nuclear reactor components.
Award Announced Date	2012-07-17T00:00:00
Awarded Institution	None
Facility	None
Facility Tech Lead	Alina Zackrone, Jeff Terry
Irradiation Facility	None
PI	James Stubbins
PI Email	[email protected]
Project Type	APS
RTE Number	355