Numerical investigation of the behaviour of internal cracks in a RPV under cyclic thermal shock loading
Abstract
A leak in the primary loop resulting in loss of coolant or a fracture in the main-steam line are both critical events in the operating of nuclear power plants. With the system under pressure, the operational conditions lead to injection of cold water into the reactor pressure vessel (RPV) in both cases.
Fields of Study & Subjects
Fatigue and fracture mechanics
Nuclear Engineering Thermal-Hydraulics
Nuclear Materials and Properties
Publication details
- Journal / source
- CRC Press eBooks
- Pages
- 345–351
- Publication date
- 17 February 2026
- Language
- EN
- Document type
- Book chapter