Testing to determine the leakage behavior of inflatable seals subject to severe accident loadings
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - OSTI as DE89008713; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- SAND--88-2237C
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20079977
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT; DYNAMIC LOADS; EXPERIMENTAL DATA; LEAKS; PERFORMANCE TESTING; PWR TYPE REACTORS; SEALS
- Descriptors DEC
- DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract DOE AC04-76DP00789
- Secondary number(s)
- CONF-890855--2.