Determination of Thermal Ageing Mechanisms in LWR Primary Circuit Pressure Boundary Material
Lead Research Organisation:
University of Bristol
Department Name: Physics
Abstract
This project will use a combination of advanced microscopy techniques to understand the changes in microstructure of the steel reactor pressure vessel (RPV) at Sizewell B (SZB) under long-term thermal ageing in-service. SZB is a Light Water Reactor with aspirations to generate low-carbon electricity beyond 2050. To demonstrate safe operation for Long Term Operation, degradation of primary circuit pressure boundary components must be understood and accounted for when modelling normal/fault scenarios.
People |
ORCID iD |
Studentship Projects
| Project Reference | Relationship | Related To | Start | End | Student Name |
|---|---|---|---|---|---|
| EP/Y528687/1 | 30/09/2023 | 29/09/2028 | |||
| 2940767 | Studentship | EP/Y528687/1 | 30/09/2024 | 29/09/2028 |