A finite element model for static strength analysis of CANDU fuel bundle
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G. Horhoianu
Abstract
A static strength analysis finite-element model has been developed using the ANSYS computer code in order to simulate the axial compression in CANDU type fuel bundle subject to hydraulic drag loads, deflection of fuel elements and stresses and displacements in the end plates. The validation of the finite-element model has been done by comparison with the out-reactor strength test results. Comparison of model predictions with the experimental results showed very good agreement. The comparative assessment reveals that SEU43 and SEU43L fuel bundles are able to withstand high flow rate without showing a significant geometric instability.
Kurzfassung
Ein Finite-Elemente-Modell wurde entwickelt, das mit Hilfe des ANSYS Codes die statische Festigkeit von CANDU Brennelementbündeln analysiert, die hydraulischen Belastungen durch Zugkräfte, Verbiegung der Brennelemente, Belastungen und Verschiebung der Endplatten ausgesetzt sind. Die Validierung des Finite-Elemente-Modells erfolgte durch Vergleich mit Testergebnissen zur Belastbarkeit ausserhalb des Reaktors. Der Vergleich der Modellvorhersagen mit den experimentellen Ergebnissen zeigte eine sehr gute Übereinstimmung. Die vergleichende Bewertung zeigt, dass SEU43 und SEU43L Brennelementbündel hohem Durchfluss ohne signifikante geometrische Instabilitäten widerstehen können.
References
1Horhoianu, G.; Moscalu, D. R.; Olteanu, G.; Ionescu, D. V.: Development of SEU43 Fuel Bundle for CANDU Type Reactors, Ann. Nuclear Energy, Vol. 2.5, No. 16, 1363–1372, Elsevier Science, January, 199810.1016/S0306-4549(98)00025-5Search in Google Scholar
2Horhoianu, G.; Olteanu, G.; Ionescu, D. V.: Preliminary SEU43L Fuel Bundle Design, Internal Report SCN No. 915, November, 2004, Pitesti, RomaniaSearch in Google Scholar
3Chung, C. H.; Ghang, S. K.; Suk, H. C.; Alavi, P.; Oldaker, I. E.: Performance of the CANFLEX fuel Bundle under mechanical flow testing, Proceedings of the 5th International Conference on CANDU Fuel, Vol. 1, 10–69, September 21–25, 1997, Toronto, CanadaSearch in Google Scholar
4Cho, M. S.; Sim, K. S.; Suk, M. C.; Chang, S.: Static Strength Analysis of CANFLEX Fuel Bundle for CANDU Fuel, Proceedings of the 6th International Conference on CANDU Fuel, 30–39, September 26–30, 1999, Niagara Falls, CanadaSearch in Google Scholar
© 2006, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
- Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV
- Determination of the exposure build-up factor in a slab using the LTSN method
- Lumped parameters analysis of the IAEA research reactor benchmark problem
- Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor
- A finite element model for static strength analysis of CANDU fuel bundle
- Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors
- Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
- Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
- Analyses of severe accident scenarios in RBMK-1500
