| 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<sup>TM</sup> 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 |