About this Abstract |
Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
Presentation Title |
Grain Growth and Mechanical Properties of Nano ZrO2 Oxide Dispersion Strengthened Mo30W |
Author(s) |
Neal Gaffin, Kelsa Palomares, Justin Milner, Caen Ang, Steven Zinkle |
On-Site Speaker (Planned) |
Neal Gaffin |
Abstract Scope |
Molybdenum alloys are ideal candidates for the metal matrix of a cermet based nuclear thermal propulsion system due to their high melting points, hydrogen compatibility, low neutron absorption cross-section, and good strength retention at high temperatures. A molybdenum alloy with 30 wt% tungsten (Mo30W) has been produced by consolidating pre-alloyed powders using spark plasma sintering. Given the high operating temperature of an NTP system (above 2500 K), run away grain growth can be an issue. Oxide dispersion strengthening with nano zirconium dioxide (ZrO2) is being considered to both strengthen the material and to pin grain boundaries at high temperatures. Pure Mo30W and samples with 1.5 and 10 wt% ZrO2 have been fabricated. These samples will undergo heat treatments up to 2200 ºC (2473 K) to compare the change in grain growth. Both hardness and compressive strength testing will be conducted to determine the strengthening effect of the YSZ additions. |
Proceedings Inclusion? |
Undecided |