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001     1019921
005     20240709082038.0
037 _ _ |a FZJ-2023-05742
100 1 _ |a Wu, Yihui
|0 P:(DE-Juel1)177040
|b 0
|u fzj
111 2 _ |a 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)
|c Washington
|d 2023-08-20 - 2023-08-25
|w USA
245 _ _ |a Experimental investigation on the depletion behavior of multi-component aerosols
260 _ _ |c 2023
336 7 _ |a Abstract
|b abstract
|m abstract
|0 PUB:(DE-HGF)1
|s 1703073128_22083
|2 PUB:(DE-HGF)
336 7 _ |a Conference Paper
|0 33
|2 EndNote
336 7 _ |a INPROCEEDINGS
|2 BibTeX
336 7 _ |a conferenceObject
|2 DRIVER
336 7 _ |a Output Types/Conference Abstract
|2 DataCite
336 7 _ |a OTHER
|2 ORCID
520 _ _ |a In 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
536 _ _ |a 1422 - Beyond Design Basis Accidents and Emergency Management (POF4-142)
|0 G:(DE-HGF)POF4-1422
|c POF4-142
|f POF IV
|x 0
700 1 _ |a Klauck, Michael
|0 P:(DE-Juel1)143718
|b 1
|u fzj
700 1 _ |a Allelein, Hans-Josef
|0 P:(DE-Juel1)130314
|b 2
909 C O |o oai:juser.fz-juelich.de:1019921
|p VDB
910 1 _ |a Forschungszentrum Jülich
|0 I:(DE-588b)5008462-8
|k FZJ
|b 0
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910 1 _ |a RWTH Aachen
|0 I:(DE-588b)36225-6
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910 1 _ |a Forschungszentrum Jülich
|0 I:(DE-588b)5008462-8
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|6 P:(DE-Juel1)143718
910 1 _ |a RWTH Aachen
|0 I:(DE-588b)36225-6
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|6 P:(DE-Juel1)130314
913 1 _ |a DE-HGF
|b Forschungsbereich Energie
|l Nukleare Entsorgung, Sicherheit und Strahlenforschung (NUSAFE II)
|1 G:(DE-HGF)POF4-140
|0 G:(DE-HGF)POF4-142
|3 G:(DE-HGF)POF4
|2 G:(DE-HGF)POF4-100
|4 G:(DE-HGF)POF
|v Sicherheit von Kernreaktoren
|9 G:(DE-HGF)POF4-1422
|x 0
914 1 _ |y 2023
920 _ _ |l yes
920 1 _ |0 I:(DE-Juel1)IEK-14-20191129
|k IEK-14
|l Elektrochemische Verfahrenstechnik
|x 0
980 _ _ |a abstract
980 _ _ |a VDB
980 _ _ |a I:(DE-Juel1)IEK-14-20191129
980 _ _ |a UNRESTRICTED
981 _ _ |a I:(DE-Juel1)IET-4-20191129

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