Published 1996
| Version v1
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Probabilistic calibration of safety coefficients for flawed components in nuclear engineering
Description
The rules that are currently under application to verify the acceptance of flaws in nuclear components rely on deterministic criteria supposed to ensure the safe operating of plants. The interest of having a precise and reliable method to evaluate the safety margins and the integrity of components led Electricite de France to launch an approach to link directly safety coefficients with safety levels. This paper presents a probabilistic methodology to calibrate safety coefficients in relation to reliability target values. The proposed calibration procedure applies to the case of a ferritic flawed pipe using the R6 procedure for assessing the integrity of the structure. (authors). 5 refs., 5 figs
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Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- EDF--96-NB-00141
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 28045566
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- DEFECTS; FAILURE MODE ANALYSIS; FERRITIC STEELS; PIPES; PLASTICITY; PROBABILISTIC ESTIMATION; SAFETY; STRESS INTENSITY FACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; STEELS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TRANSITION ELEMENT ALLOYS