STEAM-GENERATOR RELIABILITY - IMPLICATIONS FOR APWR CODES END STANDARDS

Citation
P. Whyatt et al., STEAM-GENERATOR RELIABILITY - IMPLICATIONS FOR APWR CODES END STANDARDS, Nuclear energy, 34(4), 1995, pp. 217-228
Citations number
40
Categorie Soggetti
Nuclear Sciences & Tecnology
Journal title
ISSN journal
01404067
Volume
34
Issue
4
Year of publication
1995
Pages
217 - 228
Database
ISI
SICI code
0140-4067(1995)34:4<217:SR-IFA>2.0.ZU;2-T
Abstract
Faults with steam generators have had a significant impact on the gene rating capacity of nuclear power stations worldwide. The assumption th at the service life of steam generators would be similar to that of th e other plant is no longer held to be true. This paper identifies fail ure modes experienced by steam generators and associated systems, and describes options for remedial action. Experience of steam generator r epairs and replacements ave reported, from which issues relevant for a ny codes and standards for APWR designs for the UK are identified.