Cladding failure probability modeling for risk evaluations of fast reactors [electronic resource].
- Argonne, Ill. : Argonne National Laboratory, 1987.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 9 : digital, PDF file
- Additional Creators:
- Argonne National Laboratory
United States. Department of Energy. Office of Scientific and Technical Information
- This paper develops the methodology to incorporate cladding failure data and associated modeling into risk evaluations of liquid metal-cooled fast reactors (LMRs). Current US innovative designs for metal-fueled pool-type LMRs take advantage of inherent reactivity feedback mechanisms to limit reactor temperature increases in response to classic anticipated-transient-without-scram (ATWS) initiators. Final shutdown without reliance on engineered safety features can then be accomplished if sufficient time is available for operator intervention to terminate fission power production and/or provide auxiliary cooling prior to significant core disruption. Coherent cladding failure under the sustained elevated temperatures of ATWS events serves as one indicator of core disruption. In this paper we combine uncertainties in cladding failure data with uncertainties in calculations of ATWS cladding temperature conditions to calculate probabilities of cladding failure as a function of the time for accident recovery.
- Published through SciTech Connect.
9. SMIRT: international conference on structural mechanics in reactor technology, Lausanne, Switzerland, 17 Aug 1987.
Kramer, J.M.; Mueller, C.J.
- Funding Information:
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