Published 1987
| Version v1
Book
Fatigue monitoring in nuclear power plant
Creators
- 1. Electricite de France, 93 - Saint-Denis. Direction des Etudes et Recherches
Description
For several years, Electricite de France has been developing a system for monitoring the fatigue of the critical zones of the primary circuit of its PWR plants, named 'Fatiguemeter'. A prototype was installed in January 1985 at the Bugey 2 power plant for the ongoing study, in real time, of the charging line nozzle of the cold leg. This experiment is to be extended to other zones of the reactor coolant system in 1987. The discussion here only covers the main ageing mechanism which affects the reactor coolant system, i.e. fatigue, basically originating from thermal stresses, and neglects such other aspects as irradiation, corrosion, friction and vibration, whose impact, limited, cannot be estimated with accuracy. (orig./GL)
Additional details
Publishing Information
- Publisher
- Balkema.
- Imprint Place
- Rotterdam (Netherlands)
- ISBN
- 90-6191-765-4
- Imprint Title
- Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. D
- Imprint Pagination
- 469 p.
- Journal Page Range
- p. 133-140.
Conference
- Title
- 9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19041822
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AVAILABILITY; BUGEY-2 REACTOR; DATA ACQUISITION; FATIGUE; FLOWSHEETS; LIFETIME; MODULAR STRUCTURES; ON-LINE SYSTEMS; PRIMARY COOLANT CIRCUITS; REAL TIME SYSTEMS; THERMAL STRESSES; TRANSIENTS
- Descriptors DEC
- COOLING SYSTEMS; DIAGRAMS; ENRICHED URANIUM REACTORS; INFORMATION; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STRESSES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS