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| Content Provider | The American Society of Mechanical Engineers (ASME) Digital Collection |
|---|---|
| Author | Joly, Pierre Roch, François Primault, Christophe |
| Copyright Year | 2013 |
| Abstract | The shells of the PWR heavy components are made of quenched and tempered low alloy steel (type A508 cl.3). Slow thermal ageing of the steel may occur by inter-granular segregation of impurities, depending on the service temperature and the concentration of residual elements (mainly phosphorus) in the steel. This phenomenon may generate embrittlement (i.e. a shift of ductile to brittle transition temperature). The pressurizer service temperature is the highest of the primary loop (345°C), and this component may be affected by more important ageing effects than others. In order to support rules for embrittlement predictions and to anticipate the potential embrittlement of the pressure boundary of this component, AREVA launched a research program, on different materials (base materials, weld metals, and heat affected zones of welds) based on accelerated ageing (400°C up to 30,000 hours and 450°C up to 20,000 hours), and Charpy impact toughness measurements. The aim of this paper is to present available results and to analyze them in the light of the literature and the available models. |
| Sponsorship | Pressure Vessels and Piping Division Nondestructive Evaluation Engineering Division |
| File Format | |
| ISBN | 9780791855737 |
| DOI | 10.1115/PVP2013-97643 |
| Volume Number | Volume 7: Operations, Applications and Components |
| Conference Proceedings | ASME 2013 Pressure Vessels and Piping Conference |
| Language | English |
| Publisher Date | 2013-07-14 |
| Publisher Place | Paris, France |
| Access Restriction | Subscribed |
| Subject Keyword | Temperature Metals Embrittlement Shells Steel Brittleness Pressure Fracture toughness Alloy steel Phase transition temperature Welded joints Heat Pressure vessels Pressurized water reactors |
| Content Type | Text |
| Resource Type | Article |
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