Abstract
Mechanical properties of UO 2 fuel are important to nuclear engineers to understand fuel performance in service. Obtaining accurate data is key to provide input for modeling of fuel performance during operation and accident scenarios, where enhancement of creep behavior of UO 2 at moderate temperatures is desirable. Hardness and creep data from single crystals prestrained at 1200 °C was measured between 25 and 500 °C using nanoindentation to quantify any potential enhancement of mechanical properties produced by high temperature deformation.
Original language | English (US) |
---|---|
Pages (from-to) | 623-624 |
Number of pages | 2 |
Journal | Transactions of the American Nuclear Society |
Volume | 117 |
State | Published - 2017 |
Event | 2017 Transactions of the American Nuclear Society, ANS 2017 - Washington, United States Duration: Oct 29 2017 → Nov 2 2017 |
ASJC Scopus subject areas
- Nuclear Energy and Engineering
- Safety, Risk, Reliability and Quality