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@INPROCEEDINGS{Wu:1019921,
author = {Wu, Yihui and Klauck, Michael and Allelein, Hans-Josef},
title = {{E}xperimental investigation on the depletion behavior of
multi-component aerosols},
reportid = {FZJ-2023-05742},
year = {2023},
abstract = {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},
month = {Aug},
date = {2023-08-20},
organization = {20th International Topical Meeting on
Nuclear Reactor Thermal Hydraulics
(NURETH-20), Washington (USA), 20 Aug
2023 - 25 Aug 2023},
cin = {IEK-14},
cid = {I:(DE-Juel1)IEK-14-20191129},
pnm = {1422 - Beyond Design Basis Accidents and Emergency
Management (POF4-142)},
pid = {G:(DE-HGF)POF4-1422},
typ = {PUB:(DE-HGF)1},
url = {https://juser.fz-juelich.de/record/1019921},
}