About this Abstract |
Meeting |
2020 TMS Annual Meeting & Exhibition
|
Symposium
|
Radiation Effects in Metals and Ceramics
|
Presentation Title |
Mechanical Properties of Irradiated Cladding Material from BOR-60 Irradiations |
Author(s) |
Tarik A. Saleh, Benjamin P. Eftink, Stuart A. Maloy, Gary S. Was |
On-Site Speaker (Planned) |
Tarik A. Saleh |
Abstract Scope |
Multiple engineering materials were irradiated in the BOR-60 reactor to doses of 14 dpa to 35 dpa, at a number of temperatures ranging from 375 to 525 C, as part of the Simulating Neutrons with Accelerated Particles (SNAP) project, funded through the U.S. Department of Energy, Office of Nuclear Energy. The purpose of this project is to compare fast reactor generated neutron irradiation damage to that generated from ion irradiation. The samples were in the form of 3mm diameter by 0.25mm thick TEM specimens. Mechanical properties were measured by shear punch test method, yielding effective shear stress vs displacement curves. This data can be correlated to and compared to yield and UTS data generated from tensile tests. The alloys HT9, T91, 14YWT, and 800H were tested, along with a number of model alloys. This data will be compared to control specimens, as well as samples from other irradiations. |
Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |