Email RIS file
Bookmark
Report an Issue

Steam generator tube failures [electronic resource].

Published:
Rockville, Md. : U.S. Nuclear Regulatory Commission, 1996.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:
305 pages : digital, PDF file
Additional Creators:
U.S. Nuclear Regulatory Commission and United States. Department of Energy. Office of Scientific and Technical Information
Access Online

Availability

I Want It
I Want It

Finding items...

Restrictions on Access:
Free-to-read Unrestricted online access
Summary:
A review and summary of the available information on steam generator tubing failures and the impact of these failures on plant safety is presented. The following topics are covered: pressurized water reactor (PWR), Canadian deuterium uranium (CANDU) reactor, and Russian water moderated, water cooled energy reactor (VVER) steam generator degradation, PWR steam generator tube ruptures, the thermal-hydraulic response of a PWR plant with a faulted steam generator, the risk significance of steam generator tube rupture accidents, tubing inspection requirements and fitness-for-service criteria in various countries, and defect detection reliability and sizing accuracy. A significant number of steam generator tubes are defective and are removed from service or repaired each year. This wide spread damage has been caused by many diverse degradation mechanisms, some of which are difficult to detect and predict. In addition, spontaneous tube ruptures have occurred at the rate of about one every 2 years over the last 20 years, and incipient tube ruptures (tube failures usually identified with leak detection monitors just before rupture) have been occurring at the rate of about one per year. These ruptures have caused complex plant transients which have not always been easy for the reactor operators to control. Our analysis shows that if more than 15 tubes rupture during a main steam line break, the system response could lead to core melting. Although spontaneous and induced steam generator tube ruptures are small contributors to the total core damage frequency calculated in probabilistic risk assessments, they are risk significant because the radionuclides are likely to bypass the reactor containment building. The frequency of steam generator tube ruptures can be significantly reduced through appropriate and timely inspections and repairs or removal from service.
Report Numbers:
E 1.99:nureg/cr--6365
E 1.99: inel--95/0383
inel--95/0383
nureg/cr--6365
Subject(s):
Other Subject(s):
Note:
Published through SciTech Connect.
04/01/1996.
"nureg/cr--6365"
" inel--95/0383"
"TI96010605"
Shah, V.N.; Ellison, P.G.; MacDonald, P.E.; Ward, L.W.
Funding Information:
AC07-76ID01570
View MARC record | catkey: 14801105