|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Computational Materials Engineering for Nuclear Reactor Applications
||Structural Integrity Analysis of Reactor Pressure Vessel with Lamellar Flaws in Grizzly
||Marie Backman, Benjamin Spencer, Robert H. Dodds, Brian D. Wirth
|On-Site Speaker (Planned)
Ultrasonic inspections of the reactor pressure vessels (RPV) in the Doel 3 and Tihange 2 reactors in Belgium revealed thousands of lamellar flaws, leading to a shut down of the reactors. The flaws are assumed to have formed during the fabrication of the vessels and are not expected to propagate under normal operating conditions, however, it is necessary to analyze the effect of such flaws on the structural integrity during pressurized thermal shock events.
Grizzly is a MOOSE-based multiphysics simulation code that is being developed to model material aging issues in nuclear power plants. The Grizzly efforts are currently focused on radiation embrittlement of the RPV due to long-term radiation exposure. Using Grizzly, we perform an analysis of lamellar flaws in a RPV under pressurized thermal shock loading and study the effect of flaw orientation.
||Planned: A print-only volume