Analytical TEM characterization of modified F82H and 14YW under irradiation of simultaneous helium and neutron irradiation compared to only neutron at 500 C
A RAFM steel and an ODS ferritic alloy (F82H.mod3+CW and 14YW, respectively) were irradiated as part of the JP27 irradiation experiment conducted in the High Flux Isotope Reactor to explore He effects in structural alloys. The ISHI technique is used to implant He up to 9 µm below the surface of a NiAl coated sample at He/dpa levels up to ~50. This report summarizes the current status of TEM characterization of two irradiated alloys. The He-implanted side of the RAFM alloy exhibited significant swelling due to bubble and void formation within the matrix, on pre-existing dislocations, and at interfaces within the material. The 14YW alloy exhibited significant swelling even in the absence of implanted He, primarily through large voids that formed on the ODS particles. In addition, significant radiation-induced segregation of the Cr was observed around oxide particles and on lath boundaries, and visible α' particles could be detected via elemental mapping of the matrix of the 14YW alloy.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-76RL01830
- OSTI ID:
- 1327195
- Report Number(s):
- PNNL-SA-104596; AT2030110
- Resource Relation:
- Related Information: Fusion Materials Semiannual Progress Report For the Period Ending June 30, 2014, 56:19-30. DOE/ER-0313/56
- Country of Publication:
- United States
- Language:
- English
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