Testing to determine the leakage behavior of inflatable seals subject to severe accident loadings

Conference · Sun Jan 01 04:00:00 EST 1989

OSTI ID:5916956

Parks, M. B.

Under the sponsorship of the United Sates Nuclear Regulatory Commission, Sandia National Laboratories is currently developing test validated methods to predict the pressure capacity, at elevated temperatures, of light water reactor (LWR) nuclear containment vessels subject to loads well beyond their design basis -- the so-called severe accident. Scale model tests of containments with the major penetrations represented have been carried to functional failure by internal pressurization. Also, combined pressure and elevated temperature tests of typical compression seals and gaskets, a full size personnel airlock, and of typical electrical penetration assemblies (EPAs), have been conducted in order to better understand the leakage behavior of containment penetrations (von Riesemann, et al. 1988). Because inflatable seals are also a part of the pressure boundary of some containments, it is important to understand their leakage behavior as well. This paper discusses the results of tests that were performed to better define the leakage behavior of inflatable seals when subjected to loads well beyond their design basis. 1 ref., 6 figs., 3 tabs.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5916956
• Report Number(s): SAND-88-2237C; CONF-890855-2; ON: DE89008713
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CONTAINMENT
DATA
DYNAMIC LOADS
EXPERIMENTAL DATA
INFORMATION
LEAKS
NUMERICAL DATA
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTORS
SEALS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS