Assessment of radioactive contamination in primary circuit of WWER-440 type reactors by computer code OSCAR for the decommissioning case

Laurynas Juodis (), Evaldas Maceika, Artūras Plukis, Frédéric Dacquait (), Jean-Baptiste Genin and Gilles Benier
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Laurynas Juodis: FTMC - Center for Physical Sciences and Technology [Vilnius]
Evaldas Maceika: FTMC - Center for Physical Sciences and Technology [Vilnius]
Artūras Plukis: FTMC - Center for Physical Sciences and Technology [Vilnius]
Frédéric Dacquait: LMCT - Laboratoire de Maitrise de la contamination et de la Chimie des Caloporteurs et du Tritium - SMTA - Service Mesures et modélisation des Transferts et des Accidents graves - DTN - Département Technologie Nucléaire - IRESNE - Institut de recherche sur les systèmes nucléaires pour la production d'énergie bas carbone (CEA - DES) - CEA - Commissariat à l'énergie atomique et aux énergies alternatives
Jean-Baptiste Genin: LMCT - Laboratoire de Maitrise de la contamination et de la Chimie des Caloporteurs et du Tritium - SMTA - Service Mesures et modélisation des Transferts et des Accidents graves - DTN - Département Technologie Nucléaire - IRESNE - Institut de recherche sur les systèmes nucléaires pour la production d'énergie bas carbone (CEA - DES) - CEA - Commissariat à l'énergie atomique et aux énergies alternatives
Gilles Benier: LMCT - Laboratoire de Maitrise de la contamination et de la Chimie des Caloporteurs et du Tritium - SMTA - Service Mesures et modélisation des Transferts et des Accidents graves - DTN - Département Technologie Nucléaire - IRESNE - Institut de recherche sur les systèmes nucléaires pour la production d'énergie bas carbone (CEA - DES) - CEA - Commissariat à l'énergie atomique et aux énergies alternatives

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Abstract: The article presents the results of modeling of the contamination of primary circuit of WWER-440 type reactor.The modeling has been performed using the OSCAR computer code (Nuclear research Centre in Cadarache, CEA,France), version V1.3 for decommissioning of nuclear power plants, taking into account the peculiarities of theWWER-440 reactor primary circuit, such as geometry, volumes, operational regime, materials. The results havebeen analyzed in the light of the scaling factor approach with the aim to demonstrate the modeling capabilitiesto identify the possibility of scaling factor application and to reproduce the activity correlation between difficultto measure and key nuclides. Calculated scaling factors for corrosion products are comparable with the ones ofother nuclear power plants. Calculation results of surface activity contamination confirmed the applicability of $^{60}$Co as a key radionuclide

Date: 2019-01
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Published in Progress in Nuclear Energy, 2019, 110, pp.191-198. ⟨10.1016/j.pnucene.2018.09.019⟩

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Persistent link: https://EconPapers.repec.org/RePEc:hal:journl:cea-03192034

DOI: 10.1016/j.pnucene.2018.09.019

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