In-service inspection of the primary circuit in PWRs
- 1. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Technologie
Description
The Commissariat a l'energie atomique, at the request of Electricite de France and Framatome, has developed original techniques for testing critical components of the primary circuit in PWRs. These techniques involve a very wide range of non-destructive testing methods, namely: eddy currents, in particular, with a multiple frequency device for testing steam generator pipes, studs and nuts; focused ultrasonic beams for testing all the welds of the reactor vessel and of its lid, the mixed welds of vessels and of steam generators, pressurizer lower head welds and studs from the inside; gamma radiography of the mixed welds of the vessel; televisual examination and examination by sweating of the rust-proof lining of the vessel and of its lid together. To these tests should be added acoustic emission studies which have been carried out during the hydraulic trial of the primary circuit and which are continuing at present during operation. These techniques are already in use both on reactors which have been in operation and on those which have not yet gone critical. So far, the two 900-MW Fessenheim reactor units and the Chooz reactor have been inspected successfully. (author)
Additional details
Additional titles
- Original title (French)
- Inspection en service du circuit primaire des reacteurs a eau sous pression
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna
- ISBN
- 92-0-050178-9
- Imprint Title
- Reliability problems of reactor pressure components
- Series
- Proceedings series.
- Journal Page Range
- v. 2 p. 311-328.
Conference
- Title
- Symposium on application of reliability technology to nuclear power plants.
- Dates
- 10 - 13 Oct 1977.
- Place
- Vienna, Austria.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 11511361
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EDDY CURRENT TESTING; GAMMA RADIOGRAPHY; IN-SERVICE INSPECTION; PIPES; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STEAM GENERATORS; ULTRASONIC TESTING; WELDED JOINTS
- Descriptors DEC
- ACOUSTIC TESTING; BOILERS; CONTAINERS; COOLING SYSTEMS; ELECTROMAGNETIC TESTING; INSPECTION; JOINTS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-SM--218/38.