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PANDA experimental database and further needs for containment analyses
Paladino, D., Kapulla, R., Paranjape, S., Suter, S., Hug, C., Chae, M. S., & Andreani, M. (2023). PANDA experimental database and further needs for containment analyses. Nuclear Engineering and Design, 404, 112173 (18 pp.). https://doi.org/10.1016/j.nucengdes.2023.112173
Assessment of the depressurisation and mixing effects of two spray systems in the PANDA facility, part II – simulations using GOTHIC8.3(QA)
Vázquez-Rodríguez, C., Andreani, M., Jiménez, G., Kapulla, R., Paranjape, S., Manuel Martín-Valdepeñas, J., & Paladino, D. (2023). Assessment of the depressurisation and mixing effects of two spray systems in the PANDA facility, part II – simulations using GOTHIC8.3(QA). Nuclear Engineering and Design, 403, 112120 (20 pp.). https://doi.org/10.1016/j.nucengdes.2022.112120
Assessment of the depressurization and mixing effects of two spray systems in the PANDA facility, part I - experimental results
Vázquez-Rodríguez, C., Kapulla, R., Paranjape, S., Andreani, M., Jiménez, G., Martín-Valdepeñas, J. M., & Paladino, D. (2023). Assessment of the depressurization and mixing effects of two spray systems in the PANDA facility, part I - experimental results. Nuclear Engineering and Design, 412, 112453 (11 pp.). https://doi.org/10.1016/j.nucengdes.2023.112453
PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena
Paladino, D., Kapulla, R., Paranjape, S., Suter, S., & Andreani, M. (2022). PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena. Nuclear Engineering and Design, 392, 111777 (18 pp.). https://doi.org/10.1016/j.nucengdes.2022.111777
Simulation of PANDA PE1 spray test using GOTHIC 8.3(QA)
Vázquez-Rodríguez, C., Jiménez, G., Andreani, M., Paladino, D., Paranjape, S., Kapulla, R., & Martín-Valdepeñas, J. M. (2022). Simulation of PANDA PE1 spray test using GOTHIC 8.3(QA). In 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19) (p. 35515 (16 pp.). American Nuclear Society.
Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
Andreani, M., Kapulla, R., Kelm, S., Paladino, D., & Paranjape, S. (2020). Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code. Journal of Nuclear Engineering and Radiation Science, 6(2), 021110 (18 pp.). https://doi.org/10.1115/1.4046296
Gas mixing caused by interacting heat sources. Part ii: modelling
Andreani, M., & Paranjape, S. (2020). Gas mixing caused by interacting heat sources. Part ii: modelling. Nuclear Engineering and Design, 370, 110887 (16 pp.). https://doi.org/10.1016/j.nucengdes.2020.110887
Modelling of the interaction of two heat sources simulating the thermal effects of PARs
Andreani, M., & Paranjape, S. (2019). Modelling of the interaction of two heat sources simulating the thermal effects of PARs (p. (13 pp.). Presented at the ICAPP 2019 - International congress on advances in nuclear power plants. .
Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
Andreani, M., Gaikwad, A. J., Ganju, S., Gera, B., Grigoryev, S., Herranz, L. E., … Zhang, R. (2019). Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction. Nuclear Engineering and Design, 354, 110177 (31 pp.). https://doi.org/10.1016/j.nucengdes.2019.110177
Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
Papini, D., Andreani, M., Steiner, P., Ničeno, B., Klügel, J. U., & Prasser, H. M. (2019). Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code. Nuclear Technology, 205(1-2), 153-173. https://doi.org/10.1080/00295450.2018.1505356
Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
Andreani, M., & Kapulla, R. (2018). Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code. In Vol. 6B. Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses (pp. ICONE26-82360 (11 pp.). https://doi.org/10.1115/ICONE26-82360
Multi-step planning calculations with the GOTHIC code used for the design of complex experiments in the PANDA facility
Andreani, M., Paladino, D., & Papini, D. (2018). Multi-step planning calculations with the GOTHIC code used for the design of complex experiments in the PANDA facility. Nuclear Engineering and Design, 339, 116-125. https://doi.org/10.1016/j.nucengdes.2018.09.005
Large scale experiments representing a containment natural circulation loop during an accident scenario
Kapulla, R., Mignot, G., Paranjape, S., Andreani, M., & Paladino, D. (2018). Large scale experiments representing a containment natural circulation loop during an accident scenario. Science and Technology of Nuclear Installations, 2018, 8989070 (12 pp.). https://doi.org/10.1155/2018/8989070
An exploratory work on the use of a Lagrangian-Eulerian model for simulating heat transfer of subchannels under reflooding conditions
Badillo, A., & Andreani, M. (2017). An exploratory work on the use of a Lagrangian-Eulerian model for simulating heat transfer of subchannels under reflooding conditions. Nuclear Engineering and Design, 321, 156-172. https://doi.org/10.1016/j.nucengdes.2016.11.031
Synthesis of a blind CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
Andreani, M., Daqiang, Y., Gaikwad, A. J., Ganju, S., Gera, B., Grigoryev, S., … Paladino, D. (2016). Synthesis of a blind CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction. In Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings (p. (13 pp.). OECD; NEA.
Synthesis of the OECD/NEA-PSI CFD benchmark exercise
Andreani, M., Badillo, A., & Kapulla, R. (2016). Synthesis of the OECD/NEA-PSI CFD benchmark exercise. Nuclear Engineering and Design, 299, 59-80. https://doi.org/10.1016/j.nucengdes.2015.12.029
Outcomes from the EURATOM–ROSATOM ERCOSAM SAMARA projects on containment thermal-hydraulics for severe accident management
Paladino, D., Andreani, M., Guentay, S., Mignot, G., Kapulla, R., Paranjape, S., … Visser, D. (2016). Outcomes from the EURATOM–ROSATOM ERCOSAM SAMARA projects on containment thermal-hydraulics for severe accident management. Nuclear Engineering and Design, 308, 103-114. https://doi.org/10.1016/j.nucengdes.2016.08.011
Simulation of hydrogen distribution in the containment during a severe accident with fast hydrogen-steam release
Papini, D., Andreani, M., Ničeno, B., Prasser, H. M., Steiner, P., & Klugel, J. U. (2015). Simulation of hydrogen distribution in the containment during a severe accident with fast hydrogen-steam release. In International topical meeting on nuclear reactor thermal hydraulics 2015, NURETH 2015: Vol. 2. Proceedings of NURETH-16 (pp. 1474-1487). American Nuclear Society.
Simulation of gas stratification build-up in the containment under severe accident conditions
Andreani, M. (2014). Simulation of gas stratification build-up in the containment under severe accident conditions. In International Conference on Nuclear Engineering, Proceedings, ICONE: Vol. 2B. Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22) (p. 31141 (10 pp.). https://doi.org/10.1115/ICONE22-31141
OECD/NEA HYMERES project: for the analysis and mitigation of a severe accident leading to hydrogen release into a nuclear plant containment
Paladino, D., Mignot, G., Kapulla, R., Paranjape, S., Andreani, M., Studer, E., … Dabbene, F. (2014). OECD/NEA HYMERES project: for the analysis and mitigation of a severe accident leading to hydrogen release into a nuclear plant containment. In Vol. 2. International congress on advances in nuclear power plants (ICAPP 2014) (pp. 1314-1322). American Nuclear Society (ANS).