An evaluation of the leakage potential of a personnel airlock subject to severe accident loads
A systematic investigation of the performance of light water reactor containment buildings subject to severe accident loads must include the consideration of leakage between the sealing surfaces of penetrations. As part of its work on containment integrity for the US Nuclear Regulatory Commission (USNRC), Sandia National Laboratories is developing test validated methods for predicting leakage from mechanical penetrations. The primary emphasis has been on large diameter operable penetrations, such as equipment hatches, personnel airlocks, and drywell heads. Several studies conducted for the USNRC have identified leakage from personnel airlocks as a potentially significant failure mode of containment buildings subject to severe accident loads, including Barnes et al. (1984) and Shackelford et al. (1985). Barnes et al (1984) conducted finite element analyses to predict separation of the sealing surfaces on the door and bulkhead, but they did not consider elevated temperature effects and they did not take credit for the performance of the seal material in calculating leak areas. To the author's knowledge, personnel airlock designs with flat bulkhead/door assemblies and seals have never been tested under severe accident conditions, i.e., elevated temperatures and pressure. This paper will describe preliminary analyses and plans for testing a full-size personnel airlock.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6303904
- Report Number(s):
- SAND-86-1656C; CONF-870812-5; ON: DE87006125
- Resource Relation:
- Conference: 9. SMIRT: international conference on structural mechanics in reactor technology, Lausanne, Switzerland, 17 Aug 1987; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CONTAINMENT BUILDINGS
PERFORMANCE
WATER COOLED REACTORS
DOORS
FINITE ELEMENT METHOD
LEAK TESTING
MECHANICAL TESTS
REACTOR ACCIDENTS
STRUCTURAL MODELS
ACCIDENTS
BUILDINGS
CONTAINMENT
MATERIALS TESTING
NUMERICAL SOLUTION
OPENINGS
REACTORS
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety