Abstract
Integrity assessment of reactor pressure vessels of light water reactors follows well established procedures relying on the surveillance program and defined by codes, standards and nuclear regulatory requirements. These procedures were developed in times where scientific knowledge was limited increasing therefore conservative safety margins to overcome the scientific shortcomings. Taking profit from the development of a number of test techniques and evaluation, it is possible nowadays to propose an alternative interpretation of the test results that provides a complementary information to the standard regulatory approach. In this work, the focus is on the Charpy impact test as it plays a critical role in surveillance programs monitoring reactor vessel degradation induced by neutron irradiation. The development of methodologies allowing experimental determination of fracture toughness from small size specimens triggered alternative approaches of extracting fracture toughness from the Charpy impact test. One of those approaches was recently successfully developed using the instrumented Charpy impact test from which the dynamic and static fracture toughness can be estimated with a reasonably good accuracy. This paper aims to provide an equally performant but simplified procedure allowing estimation of the master curve reference temperature, T0, from the Charpy impact transition curve applied to a large variety of reactor materials and irradiated conditions.
Original language | English |
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Article number | 105142 |
Number of pages | 8 |
Journal | International Journal of Pressure Vessels and Piping |
Volume | 208 |
DOIs | |
State | Published - Apr 2024 |
Funding
The author wishes to thank Dr Hieronymus Hein from FRAMATOME GmbH for providing the missing input data (USE) that were used in this work.
Funders | Funder number |
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Not added |
ASJC Scopus subject areas
- General Materials Science
- Mechanics of Materials
- Mechanical Engineering