NSUF 19-1802: Microstructure characterization of neutron-irradiated Fe-Cr-C model alloys
This project aims to investigate the irradiated microstructure of Fe-12Cr-0.2C ternary model alloy using transmission electron microscopy (TEM) and atom probe tomography (APT). The Fe-12Cr-0.2C system was chosen due to its importance for advanced fast reactors, as Fe-12Cr-0.2C base ferritic/martensitic (F/M) steel HT-9 cladding was used in fast reactors such as EBR-II and is also being proposed as the primary candidate cladding material for versatile test reactor and micro-reactors. The goal of this project is to advance the DOE Office of Nuclear Energy’s mission in advanced reactor technologies by bridging the knowledge gap between Fe-Cr binary model alloys and Fe-Cr base complex commercial alloy HT-9. TEM will be used to quantify the radiation-induced dislocation loops and APT will be used to quantify possible radiation-enhanced α' precipitation. The outcomes of this project will provide critical insights on the effects of carbides on the radiation response of Fe-12Cr-0.2C alloys. This project is a continuing effort of several RTEs trying to bridge the knowledge gap between simple Fe-Cr binary model alloys and Fe-Cr base complex ferritic/martensitic steels by investigating Fe-Cr-C ternary alloys using state-of-the-art characterization techniques. For instance, Fig. 1 is an example of STEM characterization of the carbides and ferritic grains in unirradiated Fe-9Cr-0.1C alloy. The irradiation conditions of the samples to be investigated include Fe-12Cr-0.02C alloys irradiated to ~0.01, 0.1, 0.5 and 1 dpa at ~300C. All the neutron irradiation experiments have been completed and the samples are readily available for post-irradiation examination (PIE). All the PIE experiments are expected to be completed within the six-month period after the proposal is awarded.
Допълнителна информация
| Поле | Стойност |
|---|---|
| Abstract | This project aims to investigate the irradiated microstructure of Fe-12Cr-0.2C ternary model alloy using transmission electron microscopy (TEM) and atom probe tomography (APT). The Fe-12Cr-0.2C system was chosen due to its importance for advanced fast reactors, as Fe-12Cr-0.2C base ferritic/martensitic (F/M) steel HT-9 cladding was used in fast reactors such as EBR-II and is also being proposed as the primary candidate cladding material for versatile test reactor and micro-reactors. The goal of this project is to advance the DOE Office of Nuclear Energy’s mission in advanced reactor technologies by bridging the knowledge gap between Fe-Cr binary model alloys and Fe-Cr base complex commercial alloy HT-9. TEM will be used to quantify the radiation-induced dislocation loops and APT will be used to quantify possible radiation-enhanced α' precipitation. The outcomes of this project will provide critical insights on the effects of carbides on the radiation response of Fe-12Cr-0.2C alloys. This project is a continuing effort of several RTEs trying to bridge the knowledge gap between simple Fe-Cr binary model alloys and Fe-Cr base complex ferritic/martensitic steels by investigating Fe-Cr-C ternary alloys using state-of-the-art characterization techniques. For instance, Fig. 1 is an example of STEM characterization of the carbides and ferritic grains in unirradiated Fe-9Cr-0.1C alloy. The irradiation conditions of the samples to be investigated include Fe-12Cr-0.02C alloys irradiated to ~0.01, 0.1, 0.5 and 1 dpa at ~300C. All the neutron irradiation experiments have been completed and the samples are readily available for post-irradiation examination (PIE). All the PIE experiments are expected to be completed within the six-month period after the proposal is awarded. |
| Award Announced Date | 2019-05-14T17:10:48.26 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Alina Zackrone, Yaqiao Wu |
| Irradiation Facility | None |
| PI | James Stubbins |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 1802 |