001019921 001__ 1019921
001019921 005__ 20240709082038.0
001019921 037__ $$aFZJ-2023-05742
001019921 1001_ $$0P:(DE-Juel1)177040$$aWu, Yihui$$b0$$ufzj
001019921 1112_ $$a20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)$$cWashington$$d2023-08-20 - 2023-08-25$$wUSA
001019921 245__ $$aExperimental investigation on the depletion behavior of multi-component aerosols
001019921 260__ $$c2023
001019921 3367_ $$0PUB:(DE-HGF)1$$2PUB:(DE-HGF)$$aAbstract$$babstract$$mabstract$$s1703073128_22083
001019921 3367_ $$033$$2EndNote$$aConference Paper
001019921 3367_ $$2BibTeX$$aINPROCEEDINGS
001019921 3367_ $$2DRIVER$$aconferenceObject
001019921 3367_ $$2DataCite$$aOutput Types/Conference Abstract
001019921 3367_ $$2ORCID$$aOTHER
001019921 520__ $$aIn the course of a severe accident, fission products from the damaged core can be released into the containment in the form of aerosols. These aerosols are radioactive and can be transported anywhere, which increases the operational safety risk. In the worst scenario, in the event of containment failure, these aerosols are released into the surrounding environment, posing a serious threat to human health. Consequently, developing a comprehensive and deep insight into the aerosol depletion behavior in a severe accident is essential to improve the prediction ability of accident progression and to contribute to the severe accident management.Various experimental test series on nuclear aerosol depletion behavior have been carried out in the IN-EX facility at the Forschungszentrum Jülich, Germany. Since comprehensive investigations on the depletion behavior of single-species and two-component aerosols have been performed recently and in the past, complementary test series with multi-component aerosols are of great interest. Consequently, based on the results of the PHÉBUS FPT3 test, a mixture of CsI/Cs2MoO4/SnO2/Ag was applied in our experiments. Where CsI and Cs2MoO4 are taken as representative soluble aerosols, while SnO2 and Ag are considered as representative insoluble aerosols. In this work, we measured the size distribution to obtain an overview of the depletion behavior of multi-component aerosols, and derived experimental aerosol removal rates to evaluate it. Moreover, we verified the experimental results of two-component aerosols with various mass ratios between soluble and insoluble aerosols, as a comparison unit to assess the results of four-component aerosols.KEYWORDS
001019921 536__ $$0G:(DE-HGF)POF4-1422$$a1422 - Beyond Design Basis Accidents and Emergency Management (POF4-142)$$cPOF4-142$$fPOF IV$$x0
001019921 7001_ $$0P:(DE-Juel1)143718$$aKlauck, Michael$$b1$$ufzj
001019921 7001_ $$0P:(DE-Juel1)130314$$aAllelein, Hans-Josef$$b2
001019921 909CO $$ooai:juser.fz-juelich.de:1019921$$pVDB
001019921 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)177040$$aForschungszentrum Jülich$$b0$$kFZJ
001019921 9101_ $$0I:(DE-588b)36225-6$$6P:(DE-Juel1)177040$$aRWTH Aachen$$b0$$kRWTH
001019921 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)143718$$aForschungszentrum Jülich$$b1$$kFZJ
001019921 9101_ $$0I:(DE-588b)36225-6$$6P:(DE-Juel1)130314$$aRWTH Aachen$$b2$$kRWTH
001019921 9131_ $$0G:(DE-HGF)POF4-142$$1G:(DE-HGF)POF4-140$$2G:(DE-HGF)POF4-100$$3G:(DE-HGF)POF4$$4G:(DE-HGF)POF$$9G:(DE-HGF)POF4-1422$$aDE-HGF$$bForschungsbereich Energie$$lNukleare Entsorgung, Sicherheit und Strahlenforschung (NUSAFE II)$$vSicherheit von Kernreaktoren$$x0
001019921 9141_ $$y2023
001019921 920__ $$lyes
001019921 9201_ $$0I:(DE-Juel1)IEK-14-20191129$$kIEK-14$$lElektrochemische Verfahrenstechnik$$x0
001019921 980__ $$aabstract
001019921 980__ $$aVDB
001019921 980__ $$aI:(DE-Juel1)IEK-14-20191129
001019921 980__ $$aUNRESTRICTED
001019921 981__ $$aI:(DE-Juel1)IET-4-20191129