Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.016 seconds
Swamy, S.A.; Bhowmick, D.C.; Prager, D.E.
Proceedings of the seminar on leak before break in reactor piping and vessels1997
Proceedings of the seminar on leak before break in reactor piping and vessels1997
AbstractAbstract
[en] The regulatory requirements for postulated pipe ruptures have changed significantly since the first nuclear plants were designed. The Leak-Before-Break (LBB) methodology is now accepted as a technically justifiable approach for eliminating postulation of double-ended guillotine breaks (DEGB) in high energy piping systems. The previous pipe rupture design requirements for nuclear power plant applications are responsible for all the numerous and massive pipe whip restraints and jet shields installed for each plant. This results in significant plant congestion, increased labor costs and radiation dosage for normal maintenance and inspection. Also the restraints increase the probability of interference between the piping and supporting structures during plant heatup, thereby potentially impacting overall plant reliability. The LBB approach to eliminate postulating ruptures in high energy piping systems is a significant improvement to former regulatory methodologies, and therefore, the LBB approach to design is gaining worldwide acceptance. However, the methods and criteria for LBB evaluation depend upon the policy of individual country and significant effort continues towards accomplishing uniformity on a global basis. In this paper the historical development of the U.S. LBB criteria will be traced and the results of an LBB evaluation for a typical Japanese PWR primary loop applying U.S. NRC approved methods will be presented. In addition, another approach using the Japanese LBB criteria will be shown and compared with the U.S. criteria. The comparison will be highlighted in this paper with detailed discussion
Primary Subject
Source
Faidy, C. (ed.) (Electricite de France, Villeurbanne (France)); Gilles, P. (ed.) (Framatome, Paris (France)); Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Electricite de France (EDF), 69 - Villeurbanne (France); Battelle, Columbus, OH (United States); 773 p; Apr 1997; p. 55-64; Seminar on leak before break in reactor piping and vessels; Lyon (France); 9-11 Oct 1995; Also available from OSTI as TI97004806; NTIS; GPO
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue