The impact of BWR MK I primary containment failure dynamics on secondary containment integrity [electronic resource].
- Published
- Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1987.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 22 : digital, PDF file
- Additional Creators
- Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- During the past four years, the ORNL BWRSAT Program has developed a series of increasingly sophisticated BWR secondary containment models. These models have been applied in a variety of studies to evaluate the severe accident mitigation capability of BWR secondary containments. This paper describes the results of a recent ORNL study of the impact of BWR MK I primary containment failure dynamics on secondary containment integrity. A 26-cell MELCOR Browns Ferry secondary containment model is described and the predicted thermodynamic response of the secondary containment to a variety of postulated primary containment failure modes is presented. The effects of primary containment failure location, timing, and ultimate hole size on secondary containment response is investigated, and the potential impact of hydrogen deflagrations on secondary containment integrity is explored.
- Report Numbers
- E 1.99:conf-8710111-6
conf-8710111-6 - Subject(s)
- Other Subject(s)
- Bwr Type Reactors
- Containment Systems
- Failures
- Blowdown
- Corium
- Design
- Fission Products
- Hydrogen
- Loss Of Coolant
- Reactor Safety
- Risk Assessment
- Thermodynamics
- Accidents
- Containment
- Elements
- Engineered Safety Systems
- Isotopes
- Materials
- Nonmetals
- Radioactive Materials
- Reactor Accidents
- Reactors
- Safety
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
01/01/1987.
"conf-8710111-6"
"DE88002534"
15. water reactor safety information meeting, Gaithersburg, MD, USA, 26 Oct 1987.
Greene, S.R. - Funding Information
- AC05-84OR21400
View MARC record | catkey: 14368415