The probability of containment failure by direct containment heating in Zion [electronic resource].
- Published
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1994.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- 385 pages : digital, PDF file
- Additional Creators
- U.S. Nuclear Regulatory Commission and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- This report is the first step in the resolution of the Direct Containment Heating (DCH) issue for the Zion Nuclear Power Plant using the Risk Oriented Accident Analysis Methodology (ROAAM). This report includes the definition of a probabilistic framework that decomposes the DCH problem into three probability density functions that reflect the most uncertain initial conditions (UO₂ mass, zirconium oxidation fraction, and steel mass). Uncertainties in the initial conditions are significant, but our quantification approach is based on establishing reasonable bounds that are not unnecessarily conservative. To this end, we also make use of the ROAAM ideas of enveloping scenarios and ``splintering.`` Two causal relations (CRs) are used in this framework: CR1 is a model that calculates the peak pressure in the containment as a function of the initial conditions, and CR2 is a model that returns the frequency of containment failure as a function of pressure within the containment. Uncertainty in CR1 is accounted for by the use of two independently developed phenomenological models, the Convection Limited Containment Heating (CLCH) model and the Two-Cell Equilibrium (TCE) model, and by probabilistically distributing the key parameter in both, which is the ratio of the melt entrainment time to the system blowdown time constant. The two phenomenological models have been compared with an extensive database including recent integral simulations at two different physical scales. The containment load distributions do not intersect the containment strength (fragility) curve in any significant way, resulting in containment failure probabilities less than 10{sup −3} for all scenarios considered. Sensitivity analyses did not show any areas of large sensitivity.
- Report Numbers
- E 1.99:nureg/cr--6075
E 1.99: sand--93-1535
sand--93-1535
nureg/cr--6075 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
12/01/1994.
"nureg/cr--6075"
" sand--93-1535"
"TI95005275"
"GB0103012"
Theofanous, T.G.; Pilch, M.M.; Yan, H. - Type of Report and Period Covered Note
- Topical; 12/01/1994 - 12/01/1994
- Funding Information
- AC04-94AL85000
View MARC record | catkey: 14358246