Safety margin predictions of reactor pressure vessel integrity assessment procedures for pressurized thermal shocks
Year: 2025
Type: article
Abstract: The integrity assessment of a reactor pressure vessel in a loss of coolant scenario with pressurized thermal shock (PTS) loading of the vessel wall is a crucial part of the safety review for the long-term operation, since the embrittlement of the vessel steel due to neutron irradiation continues during the ongoing operation. The procedures for the safety demonstration in different countries select different options for this assessment, namely concerning crack postulates, weld residual stresses, fracture toughness model, and warm pre-stress model. In order to understand the impact of these differences, the deterministic procedures of eight European countries are applied to two different example cases, which are based on the Konvoi and the VVER-440 plant type but are partly fictitious and not reflecting any particular unit. The safety margin in terms of ductile–brittle transition temperature is computed for each assessment, allowing to draw conclusions regarding the impact of different options within an assessment. In addition, it is possible to identify general trends of the procedures concerning their safety margin prediction.
Source: Nuclear Engineering and Design
Authors: Klaus Heckmann, Jens Arndt, Jürgen Sievers, Ulrike Läuferts, Uwe Jendrich, Sara Beck, Frank Michel
Institution: Gesellschaft für Anlagen und Reaktorsicherheit
Language: English
Subfield: Mechanics of Materials
Field: Engineering
Domain: Physical Sciences
Open Access status: hybrid
Estimated APC paid: $2,710
OpenAlex ID: W4413990714