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dc.contributor.authorGYOERI Csabaen_GB
dc.contributor.authorVAN UFFELEN PAULen_GB
dc.contributor.authorSCHUBERT ARNDTen_GB
dc.contributor.authorVAN DE LAAR JACQUESen_GB
dc.contributor.authorHOZER Z.en_GB
dc.date.accessioned2010-02-25T14:47:34Z-
dc.date.available2005-12-12en_GB
dc.date.available2010-02-25T14:47:34Z-
dc.date.issued2005en_GB
dc.date.submitted2005-11-22en_GB
dc.identifier.citationProceedings of the 6th International Conference on WWER Fuel Performance, Modeling and Experimental Supporten_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC31288-
dc.description.abstractThe paper gives an overview of the recent WWER-specific development and validation of the TRANSURANUS fuel performance code in the range of accident conditions. The extension of the code applicability was achieved through the implementation of new correlations for plastic deformation, steam oxidation and failure of the Zr1%Nb (E110) cladding at high temperature up to 1200 oC. The development of the new correlations was based on a comprehensive database of steam oxidation tests, tensile tests, tube burst tests and ring compression tests carried out at the KFKI Atomic Energy Research Institute (AEKI). The most important results of the separate effect tests are summarized in the first part of the paper exposing the interference of oxygen uptake, mechanical strength and cladding ductility. The newly developed empirical correlations, presented in the second part of the paper, were incorporated into the TRANSURANUS code and validated against independent tube burst tests. The results of numerous post-test analyses and an example for the simulation of fuel rod performance in postulated large break loss of coolant accident (LOCA) are presented in the third and last part of the paper. Furthermore, a new method is introduced to evaluate the fuel rod embrittlement at the quenching of the core on the basis of a ductility parameter which is independent from any oxidation correlation.en_GB
dc.description.sponsorshipJRC.E.3-Materials researchen_GB
dc.format.mediumPrinteden_GB
dc.languageENGen_GB
dc.publisherInstitute for Nuclear Research (INRNE)en_GB
dc.relation.ispartofseriesJRC31288en_GB
dc.titleImplementing Experimental Data on the Accidential Behaviour of the WWER Cladding Obtained at the AEKI in the TRANSURANUS Fuel Performance Codeen_GB
dc.typeArticles in periodicals and booksen_GB
JRC Directorate:Nuclear Safety and Security

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