Main Steam Line Break Analysis for Lungmen ABWR
This course discusses the behaviors of fuel rod, vessel, and containment in Lungmen ABWR.
Credit: 2 PDH
Instructor: Ramon J. Figueroa, MSME, PE, EdD
In this two hour course, the engineer will learn about a complete flow chart for analyzing the nuclear system transient, such as behaviors of fuel rod, vessel, and containment. The double-ended MSLB transient in Lungmen ABWR is the main subject. Additionally, this course explores the TRACE, PARCS, and FRAPTRAN codes for analyzing the nuclear system transient. Using these three models, this course also explores how the models were combined for more powerful analysis including MSLB transient prediction, RPV integrity, fuel rod integrity, and containment integrity.
Throughout this course, engineers explore the analysis methods key to designing safe nuclear power plants. Engineers will also discover methods for combining traditional models in order to reach more in-depth analysis for nuclear reactor characteristics and thermo-mechanical behavior. Engineers taking this course will become more familiar with the TRACE, PARCS, and FRAPTRAN models and their applications for safety analysis. The safety analysis of nuclear power plants will take place through the lens of a real-world example, the Lungmen ABWR nuclear power plant in Taiwan.
At the end of this course, you should be able to:
|Certificate||Yes. Instant download after completing the course.|
|CEU/PDH||0.2 CEU / 2 PDH|
|Devices||Desktop, Tablet, Mobile|