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Computational modeling and validation of a modified Marple cascade impactor

by Vineet Kumar, Yadukrishnan Sasikumar, Rosemary A Montgomery
Publication Type
Conference Paper
Book Title
CFD4NRS-9 Workshop
Publication Date
Page Numbers
54 to 65
Conference Name
Computational Fluid Dynamics for Nuclear Reactor Safety Workshop (CFD4NRS-9)
Conference Location
College Station, Texas, United States of America
Conference Sponsor
NEA Working Group on Analysis and Management of Accidents (WGAMA)
Conference Date
-

Oak Ridge National Laboratory (ORNL) is investigating respirable aerosol fractions from failed high-burnup (HBU) commercial spent nuclear fuel (CSNF) rods (Montgomery et al., 2022). The work aims to characterize the source term of radioactive aerosols that could result from mechanical failure and handling of failed fuel rods during storage and/or transportation. The experiment involves capturing and characterizing aerosols from a four-point bending experiment of fueled rod segments at ORNL’s Irradiated Fuels Examination Laboratory (IFEL). For this, a Marple cascade impactor (Series 290) with the ability to collect particles up to aerodynamic equivalent diameters of ~15 μm was tested for feasibility. The commercially available Marple cascade impactor design was modified for the experiment, where the cascade inlet was replaced with a 3D printed inlet nozzle. Collection efficiency curves were then generated with the modified impactor, and the cascade’s performance was tested using ISO dust capture experiments followed by SEM analysis of the collection and computational modeling. The current work highlights the performance testing and experimental validation of this modified Marple Impactor for spent nuclear fuel aerosol collection.