Published 2005
| Version v1
Miscellaneous
EU-project SMILE / Validation of the WPS effect with a component like cylindrical specimen
- 1. Materials Testing Institute, University of Stuttgart, Pfaffenwaldring 32, D 70569 Stuttgart (Germany)
- 2. Materials Testing Institute University of Stuttgart, MPA Stuttgart, Otto-Graf-Institute (FMPA), Pfaffenwaldring 32, D - 70569 Stuttgart (Vaihingen) (Germany)
- 3. EDF, Reactor Pressure Vessel Life Management, EDF- Energy Branch - DPN, Nuclear Power Plants Support Center, Site Cap Ampere - 1 Place Pleyel, 93282 Saint Denis Cedex (France)
- 4. EDF- R and D, Departement MMC, Site des Renardieres, 77818 Meret-sur-loing cedex (France)
Description
The Reactor Pressure Vessel (RPV) is an essential component, which is liable to limit the lifetime duration of PWR plants. The assessment of defects in RPV subjected to pressurized thermal shock (PTS) transients made at an European level generally does not necessarily consider the beneficial effect of the load history (Warm Pre-stress, WPS). The SMILE project - Structural Margin Improvements in aged embrittled RPV with Load history Effects - aims to give sufficient elements to demonstrate, to model and to validate the beneficial WPS effect. The project includes significant experimental work on WPS type experiments with C(T) specimens and a PTS type transient experiment on a large component. (authors)
Additional details
Publishing Information
- Publisher
- Autorite de Surete Nucleaire
- Imprint Place
- Dijon (France)
- Imprint Title
- NuPEER Dijon 2005 Symposium. Ageing issues in nuclear power plants
- Imprint Pagination
- 404 p.
- Journal Page Range
- p. 248-266
- Report number
- INIS-FR--4368
Conference
- Title
- symposium on ageing issues in nuclear power plants
- Acronym
- NuPEER 2005
- Dates
- 22-24 Jun 2005
- Place
- Dijon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 37121664
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; EMBRITTLEMENT; LIFE SPAN; LOADING; PRESSURE VESSELS; PWR TYPE REACTORS; TESTING; THERMAL FATIGUE; THERMAL SHOCK; TRANSIENTS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; FATIGUE; MATERIALS HANDLING; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs., 14 figs., 2 tabs. Imprint:PowerPoint presentation of the workshop talks are available on www.asn.gouv.fr/nupeer/sommaire.asp.