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dc.contributor.authorGONZÁLEZ-ROBLES Ernestoen_GB
dc.contributor.authorMETZ V.en_GB
dc.contributor.authorWEGEN Detlefen_GB
dc.contributor.authorHERM M.en_GB
dc.contributor.authorPAPAIOANNOU Dimitriosen_GB
dc.contributor.authorBOHNERT E.en_GB
dc.contributor.authorGRETTER Ralfen_GB
dc.contributor.authorMÜLLER Nikolausen_GB
dc.contributor.authorNASYROW Ramilen_GB
dc.contributor.authorDE WEERD Wimen_GB
dc.contributor.authorWISS Thierryen_GB
dc.contributor.authorKIENZLER B.en_GB
dc.date.accessioned2016-12-15T02:08:46Z-
dc.date.available2016-12-13en_GB
dc.date.available2016-12-15T02:08:46Z-
dc.date.created2016-12-07en_GB
dc.date.issued2016en_GB
dc.date.submitted2016-08-02en_GB
dc.identifier.citationJOURNAL OF NUCLEAR MATERIALS vol. 479 p. 67-75en_GB
dc.identifier.issn0022-3115en_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC102738-
dc.description.abstractDuring reactor operation the fission gases Kr and Xe are formed within the UO2 matrix of nuclear fuel. Their quantification is important to evaluate their impact on critical parameters regarding the fuel behaviour during irradiation and (long-term) interim storage, such as internal pressure of the fuel rod and fuel swelling. Moreover the content of Kr and Xe in the plenum of a fuel rod and their content in the UO2 fuel itself are widely used as indicators for the release properties of 129I, 137Cs, and other safety relevant radionuclides with respect to final disposal of spent nuclear fuel. The present study deals with the fission gas release from spent nuclear fuel exposed to simulated groundwater in comparison with the fission gas previously released to the fuel rod plenum during irradiation in reactor. In a unique approach we determined both the Kr and Xe inventories in the plenum by means of a puncturing test and in leaching experiments with a cladded fuel pellet and fuel fragments in bicarbonate water under 3.2 bar H2 overpressure. The fractional inventory of the fission gases released during irradiation into the plenum was (8.3 ± 0.9) %. The fraction of inventory of fission gases released during the leaching experiments was (17 ± 2) % after 333 days of leaching of the cladded pellet and (25 ± 2) % after 447 days of leaching of the fuel fragments, respectively. The relatively high release of fission gases in the experiment with fuel fragments was caused by the increased accessibility of water to the Kr and Xe occluded in the fuel.en_GB
dc.description.sponsorshipJRC.G.III.8-Waste Managementen_GB
dc.format.mediumPrinteden_GB
dc.languageENGen_GB
dc.publisherELSEVIER SCIENCE BVen_GB
dc.relation.ispartofseriesJRC102738en_GB
dc.titleDetermination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditionsen_GB
dc.typeArticles in periodicals and booksen_GB
dc.identifier.doi10.1016/j.jnucmat.2016.06.035en_GB
JRC Directorate:Nuclear Safety and Security

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