Algorithmic determination of fuel rod cladding burst time at elevated temperatures
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G. Sauer
Abstract
The integrity of fuel rod claddings during a loss of coolant accident (LOCA) is usually assessed by comparing calculated stresses or strains with the corresponding failure thresholds. Alternatively, the cladding integrity could also be evaluated on the basis of the time elapsed since the LOCA onset. To apply this assessment criterion the relationship between failure time and cladding loading must be available. The relationship can be established computationally by monitoring the evaluation of cladding inner and outer radius during the high temperature creep process. The cladding is classified as defective when the predicted inner radius equals or exceeds the anticipated outer radius. Using a suitable creep rate correlation it is shown which results are yielded by this procedure.
Kurzfassung
Die Integrität von Brennstabhüllrohren während eines Kühlmittelverluststörfalls (KMV) wird üblicherweise anhand eines Vergleichs berechneter Hüllrohrspannungen oder-dehnungen mit den entsprechenden Versagensschwellen bewertet. Alternativ könnte die Hüllrohrintegrität auch anhand der Zeit, die seit Beginn des KMV verstrichen ist, bewertet werden. Um dieses Beurteilungskriterium anwenden zu können, müssen die Beziehungen zwischen den Hüllrohrbelastungen und der Versagenszeit bekannt sein. Sie können rechnerisch mittels der Beobachtung der Entwicklung von Innen- und Außenradius des Hüllrohrs während des Hochtemperaturkriechvorgangs ermittelt werden. Das Hüllrohr wird als defekt klassifiziert, wenn der voraussichtliche Innenradius gleich oder größer dem voraus geschätzten Außenradius ist. Unter Benutzung einer geeigneten Kriechratenkorrelation wird gezeigt, zu welchen Ergebnissen dieses Verfahren führt.
References
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© 2010, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- European clearinghouse on nuclear power plants operational experience feedback
- Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor
- Heat transfer to the building structures of the Ignalina NPP accident localisation system
- Algorithmic determination of fuel rod cladding burst time at elevated temperatures
- Development of a decommissioning strategy for the MR research reactor
- Neutron transmutation doping conceptual design
- Design optimization of shell-and-tube heat exchangers using single objective and multiobjective particle swarm optimization
- Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry
- Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering
- An analytical solution for the one-dimensional time-dependent SN transport equation for bounded and unbounded domains in cartesian geometry
- Accurate critical slab calculations for various degrees of anisotropy and for different reflection coefficients
- Technical Notes/Technische Mitteilungen
- The boundary problem in the 1D-CANDLE burn-up reactor
