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A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design
Radman, S., Fiorina, C., Mikityuk, K., & Pautz, A. (2019). A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design. Nuclear Engineering and Design, 355, 110291 (17 pp.). https://doi.org/10.1016/j.nucengdes.2019.110291
A methodology for evaluating weighting functions using MCNP and its application to PWR ex-core analyses
Pecchia, M., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2017). A methodology for evaluating weighting functions using MCNP and its application to PWR ex-core analyses. Annals of Nuclear Energy, 105, 121-132. https://doi.org/10.1016/j.anucene.2017.03.008
A mm<sup>3</sup> fiber-coupled scintillator for in-core thermal neutron detection in CROCUS
Vitullo, F., Lamirand, V., Mosset, J. B., Frajtag, P., Pakari, O., Perret, G., & Pautz, A. (2020). A mm3 fiber-coupled scintillator for in-core thermal neutron detection in CROCUS. IEEE Transactions on Nuclear Science, 67(4), 625-635. https://doi.org/10.1109/TNS.2020.2977530
A reduced order accelerator for time-dependent segregated neutronic solvers
Fiorina, C., Radman, S., Scolaro, A., & Pautz, A. (2018). A reduced order accelerator for time-dependent segregated neutronic solvers. Annals of Nuclear Energy, 121, 177-185. https://doi.org/10.1016/j.anucene.2018.07.032
Adsorption of Ba and <sup>226</sup>Ra on illite: a comparative experimental and modelling study
Marques Fernandes, M., Klinkenberg, M., Baeyens, B., Bosbach, D., & Brandt, F. (2023). Adsorption of Ba and 226Ra on illite: a comparative experimental and modelling study. Applied Geochemistry, 159, 105815 (18 pp.). https://doi.org/10.1016/j.apgeochem.2023.105815
An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor
Lamirand, V., Laureau, A., Rochman, D., Perret, G., Gruel, A., Leconte, P., … Pautz, A. (2019). An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor. In O. Serot & A. Chebboubi (Eds.), EPJ web of conferences: Vol. 211. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications (p. 03003 (5 pp.). https://doi.org/10.1051/epjconf/201921103003
Analysis of Rostov-II benchmark using conventional two-step code systems
Jang, J., Hursin, M., Lee, W., Pautz, A., Papadionysiou, M., Ferroukhi, H., & Lee, D. (2022). Analysis of Rostov-II benchmark using conventional two-step code systems. Energies, 15(9), 3318 (24 pp.). https://doi.org/10.3390/en15093318
Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels
Brankov, V., Khvostov, G., Mikityuk, K., Pautz, A., Restani, R., Abolhassani, S., … Wiesenack, W. (2016). Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels. Nuclear Engineering and Design, 305, 559-568. https://doi.org/10.1016/j.nucengdes.2016.06.021
Analysis of fuel rod behaviour in a EPR&lt;sup&gt;TM&lt;/sup&gt; during the base irradiation and LOCA-transient utilizing the FALCON code
Yun, Y., Khvostov, G., Freixa, J., & Zimmermann, M. A. (2011). Analysis of fuel rod behaviour in a EPRTM during the base irradiation and LOCA-transient utilizing the FALCON code. In Proceedings of the 2010 LWR fuel performance/top fuel/WRFPM (pp. 345-353). American Nuclear Society.
Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code
Jo, Y., Hursin, M., Lee, D., Ferroukhi, H., & Pautz, A. (2018). Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code. Annals of Nuclear Energy, 111, 141-151. https://doi.org/10.1016/j.anucene.2017.08.061
Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
Lamirand, V., Rais, A., Pakari, O., Hursin, M., Laureau, A., Pohlus, J., … Pautz, A. (2021). Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 21010 (9 pp.). https://doi.org/10.1051/epjconf/202124721010
Analysis of the preliminary campaign for the PETALE program
Laureau, A., Gruel, A., Lamirand, V., Ligonnet, T., Sardet, A., & Pautz, A. (2023). Analysis of the preliminary campaign for the PETALE program. EPJ Nuclear Sciences and Technologies, 9, 25 (9 pp.). https://doi.org/10.1051/epjn/2023010
Analytical investigations of irradiated inert matrix fuel
Restani, R., Martin, M., Kivel, N., & Gavillet, D. (2009). Analytical investigations of irradiated inert matrix fuel. Journal of Nuclear Materials, 385(2), 435-442. https://doi.org/10.1016/j.jnucmat.2008.12.030
Application of causality analysis on nuclear reactor systems
Chionis, D., Dokhane, A., Ferroukhi, H., & Pautz, A. (2019). Application of causality analysis on nuclear reactor systems. Chaos: An Interdisciplinary Journal of Nonlinear Science, 29(4), 043126 (16 pp.). https://doi.org/10.1063/1.5083905
Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface
Khvostov, G., Lyon, W., & Zimmermann, M. A. (2013). Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface. Annals of Nuclear Energy, 62, 398-412. https://doi.org/10.1016/j.anucene.2013.07.002
Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
Siefman, D., Hursin, M., Perret, G., & Pautz, A. (2020). Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments. Progress in Nuclear Energy, 121, 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245
Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies
Fiorina, C., Scolaro, A., Siefman, D., Hursin, M., & Pautz, A. (2020). Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies. Journal of Nuclear Engineering, 1(1), 54-62. https://doi.org/10.3390/jne1010005
Assessment of nTRACER and PARCS performance for VVER configurations
Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2020). Assessment of nTRACER and PARCS performance for VVER configurations. Nuclear Science and Engineering, 194(11), 1056-1066. https://doi.org/10.1080/00295639.2020.1753418
Assessment of nTRACER and parcs performance for VVER configurations
Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2019). Assessment of nTRACER and parcs performance for VVER configurations. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019) (pp. 700-709). American Nuclear Society (ANS).
Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations
Vasiliev, A., Pecchia, M., Rochman, D., Perret, G., Ferroukhi, H., Laureau, A., … Pautz, A. (2020). Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations. In Z. Ge, N. Shu, Y. Chen, W. Wang, & H. Zhang (Eds.), EPJ web of conferences: Vol. 239. ND 2019: international conference on nuclear data for science and technology (p. 22001 (6 pp.). https://doi.org/10.1051/epjconf/202023922001
 

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