% IMPORTANT: The following is UTF-8 encoded. This means that in the presence
% of non-ASCII characters, it will not work with BibTeX 0.99 or older.
% Instead, you should use an up-to-date BibTeX implementation like “bibtex8” or
% “biber”.
@INPROCEEDINGS{Chae:1022272,
author = {Chae, Myeong-Seon and Paladino, Domenico and Kelm, Stephan},
title = {{A}nalyses of {J}et-{B}uoyant {F}low in a
{M}ulti-{C}ompartment {C}ontainment using an {O}pen-{S}ource
{S}olver},
reportid = {FZJ-2024-01390},
year = {2023},
abstract = {Hydrogen mixing and distribution in a nuclear power plant
containment during a postulated severeaccident is a
phenomenon with high safety relevance for current and
advanced LWR. The OECD/NEASETHproject was carried out to
generate the experimental data on basic containment
phenomena with therequired instrumentation to assess CFD and
LP codes.In this paper, we analyzed the PANDA Test 16 of the
OECD/NEA-SETH project by usingcontainmentFOAM which is a
tailored open-source CFD code package for containment
analysisdeveloped at Forschungszentrum Jülich (Germany)
based on OpenFOAM® v9. SETH Test 16 addressedsteam-air
mixture transport driven by jets and plumes in the
multi-compartment PANDA facility (Vessel 1,Vessel 2 and
Interconnecting pipe, IP) at Paul Scherrer Institut
(Switzerland). Steam is injected with 0.040kg/s and 140 ºC
in Vessel 1 which is initially filled with dry air at 108
ºC and created a wall-plume.Steam-air mixtures are vented
out from Vessel 2. The system pressure is constant at 1.3
bar for the wholetest duration (4000 s).Sensitive studies
have been performed considering different models for the
buoyancy turbulenceproduction and dissipation terms in k-w
SST model. The distribution of steam molar fraction
andtemperature are well expected above the injection tube in
Vessel 1 and over the height of Vessel 2. While,below the
injection tube in Vessel 1 some discrepancies between the
simulations and experimental resultswere
observed.KEYWORDSPANDA, Multi-compartment, Buoyancy
turbulence model, CFD, containmentFOAM},
month = {Jan},
date = {2023-01-20},
organization = {20th International Topical Meeting on
Nuclear Reactor Thermal Hydraulics
(NURETH-20), Washington (USA), 20 Jan
2023 - 25 Jan 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/1022272},
}