THE CASE FOR ENDURANCE TESTING OF SODIUM-HEATED STEAM-GENERATORS

Citation
At. Onesto et al., THE CASE FOR ENDURANCE TESTING OF SODIUM-HEATED STEAM-GENERATORS, Nuclear technology, 103(2), 1993, pp. 168-186
Citations number
12
Categorie Soggetti
Nuclear Sciences & Tecnology
Journal title
ISSN journal
00295450
Volume
103
Issue
2
Year of publication
1993
Pages
168 - 186
Database
ISI
SICI code
0029-5450(1993)103:2<168:TCFETO>2.0.ZU;2-S
Abstract
After operating pressurized water reactor (PWR) steam generators in U. S. nuclear plants during the past 33 Yr and plugging thousands of tube s and replacing numerous steam generators at immense costs, utility an d steam generator designers are now confident that they can design, bu ild, and operate PWR steam generators successfully. Deployment of liqu id-metal fast breeder reactors (LMFBRs) will likely follow the same sc enario if long-term testing is not performed and development completed prior to commercial deployment. A case is made for endurance testing of steam generators to be used in future LMFBRs.