Published 1989 | Version v1
Report Restricted

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

Creators

  • 1. Sandia National Labs., Albuquerque, NM (USA)

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

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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.