Search Results - "Cappia, F."

Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation by Barani, T., Pizzocri, D., Cappia, F., Luzzi, L., Pastore, G., Van Uffelen, P.

“…We propose a model describing the HBS formation and the progressive intra-granular xenon depletion in UO2. The HBS formation is modeled employing the…”
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Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5% FIMA by Cappia, F., Tanaka, K., Kato, M., McClellan, K., Harp, J.

“…We present post-irradiation examination results on two type of annular mixed oxide fuel pins irradiated in the Fast Flux Test Facility (FFTF) sodium cooled…”
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Post-irradiation examinations of UO2 composites as part of the Accident Tolerant Fuels Campaign by Cappia, F., Harp, J.M., McCoy, K.

“…Enhanced thermal conductivity uranium dioxide composites containing silicon carbide (UO2−SiC) and diamond (UO2-diamond) have been irradiated to low burnup. The…”
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Nanoindentation testing of high burn-up fast reactor mixed oxide fuel by Frazer, D., Cappia, F., Miller, B., Murray, D., Winston, A., Pomo, A., White, J.T.

“…Continued research into the mechanical properties of nuclear fuel is necessary to improve modeling of the pellet-cladding mechanical interactions that occur in…”
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Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements by Pavlov, T.R., Middlemas, S.C., Miller, B.D., Cappia, F., Cole, J.I., Giglio, J.J.

“…This study presents the first thermal conductivity measurements performed on neutron irradiated U3Si2 dispersion fuel cladded in an aluminum matrix (in a plate…”
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Electron microscopy characterization of the fuel-cladding interaction in medium burnup annular fast reactor MOX by Cappia, F., Winston, A., Miller, B., Kombaiah, B., Teng, F., Murray, D., Frazer, D., Harp, J.M.

“…In this work, we present electron microscopy data focused on the fuel-cladding interaction layer in annular fast reactor MOX with HT-9 cladding at medium…”
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Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG) by Cappia, F., Miller, B.D., Aguiar, J.A., He, L., Murray, D.J., Frickey, B.J., Stanek, J.D., Harp, J.M.

“…The composition and crystal structure of the “Joint Oxyde Gaine” (JOG) has been investigated by means of electron microscopy. Microstructural characterization…”
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Post-irradiation characterization of a high burnup mixed oxide fuel rod with minor actinides by Frazer, D., Cappia, F., Harp, J.M., Medvedev, P.G., McClellan, K.J., Voit, S.L., Giglio, J., Jädernäs, D., Hosemann, P.

“…The Advanced Fuels Campaign performed a series of irradiation tests of minor actinide-bearing mixed oxide fuel (MA-MOX), the so-called AFC-2C&D experiments, to…”
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Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel by Genoni, R., Pizzocri, D., Antonello, F., Barani, T., Luzzi, L., Pavlov, T.R., Giglio, J.J., Cappia, F.

“…This work applies reconstruction methods based on a genetic algorithm to derive 3D material properties, namely porosity and percolation fraction, in irradiated…”
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Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels by Cappia, F., Pizzocri, D., Schubert, A., Van Uffelen, P., Paperini, G., Pellottiero, D., Macián-Juan, R., Rondinella, V.V.

“…A new methodology is introduced to analyse porosity data in the high burnup structure. Image analysis is coupled with the adaptive kernel density estimator to…”
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3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms by Pizzocri, D., Genoni, R., Antonello, F., Barani, T., Cappia, F.

“…This paper introduces a method to reconstruct the three-dimensional (3D) microstructure of two-phase materials, e.g., porous materials such as highly…”
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3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms by Pizzocri, D, Genoni, R, Antonello, F, Barani, T, Cappia, F

“…This paper introduces a method to reconstruct the three-dimensional (3D) microstructure of two-phase materials, e.g., porous materials such as highly…”
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Laser melting of nano-crystalline uranium dioxide by Cappia, F., Jovani-Abril, R., Spino, J., Luzzi, L., Janßen, A., Manara, D.

“…The present work is focused on the investigation of possible melting temperature depression of nano-crystalline UO2. The behaviour of nano-crystalline…”
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High-temperature and melting behaviour of nanocrystalline refractory compounds: an experimental approach applied to thorium dioxide by F Cappia, D Hudry, E Courtois, A Janßen, L Luzzi, R J M Konings, D Manara

“…The behaviour from 1500 K up to melting of nanocrystalline (nc) thorium dioxide, the refractory binary oxide with the highest melting point (3651 K), was…”
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Length scale effects of micro- and meso‑scale tensile tests of unirradiated and irradiated Zircaloy-4 cladding by Lam, S., Frazer, D., Cappia, F., Nelson, M., Samuha, S., Pitts, S., Harris, B., Hosemann, P.

“…Zircaloy-4 is an essential material for cladding structures within fission-based reactors. To explore the changes in properties measured on differing length…”
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Post-irradiation examinations of UO 2 composites as part of the Accident Tolerant Fuels Campaign by Cappia, F., Harp, J.M., McCoy, K.

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Post irradiation examinations of FeCrAl cladding in PWR conditions by Colldeweih, A.W., Petersen, P.G., Matos, M.D., Stockwell, J.A., Hansen, R.S., Kamerman, D.W., Lutz, D., Cappia, F.

“…FeCrAl alloys have been one of the prominent Accident Tolerant Fuel (ATF) cladding material candidates, primarily due to their excellent oxidation resistance…”
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Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing by Cappia, F., Wright, K., Frazer, D., Bawane, K., Kombaiah, B., Williams, W., Finkeldei, S., Teng, F., Giglio, J., Cinbiz, M.N., Hilton, B., Strumpell, J., Daum, R., Yueh, K., Jensen, C., Wachs, D.

“…Experimental investigations of the fuel microstructure and volatile fission products along the pellet of a high burnup specimen (local burnup 76 GWd/tHM) have…”
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Grain subdivision and structural modifications by high-energy heavy ions in UO2 with different initial grain size by Cappia, F., Cullison, M., Chen, T., Kombaiah, B., Bawane, K., Teng, F., Madden, J., Perez, E., Yao, T., Lei, P., Lian, J., Miao, Y., Mo, K.

“…Irradiation with 84 MeV Xe ions at peak fluence above 7 × 1017 ions/cm2 has been carried out on two UO2 samples with different initial grain sizes at 300 °C…”
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A semi-empirical model for the formation and depletion of the high burnup structure in UO2 by Pizzocri, D., Cappia, F., Luzzi, L., Pastore, G., Rondinella, V.V., Van Uffelen, P.

“…In the rim zone of UO2 nuclear fuel pellets, the combination of high burnup and low temperature drives a microstructural change, leading to the formation of…”
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