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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
Analysis of fission product transport in unit 3 of Fukushima Daiichi
Fernandez Moguel, L., Lind, T., & Rýdl, A. (2019). Analysis of fission product transport in unit 3 of Fukushima Daiichi. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2019). La Grange Park: American Nuclear Society (ANS).
Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: fission product release and transport analysis
Fernandez-Moguel, L., Rydl, A., & Lind, T. (2019). Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: fission product release and transport analysis. Annals of Nuclear Energy, 130, 93-106. https://doi.org/10.1016/j.anucene.2019.02.017
Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator
Kromer, H., Adams, R., Soubelet, B., Zboray, R., & Prasser, H. M. (2019). Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator. Applied Radiation and Isotopes, 145, 47-54. https://doi.org/10.1016/j.apradiso.2018.12.009
Pool CFD modelling: lessons from the SESAME project
Moreau, V., Profir, M., Alemberti, A., Frignani, M., Merli, F., Belka, M., … Martelli, D. (2019). Pool CFD modelling: lessons from the SESAME project. Nuclear Engineering and Design, 355, 110343 (12 pp.). https://doi.org/10.1016/j.nucengdes.2019.110343
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
Feasibility study of using a compact deuterium-deuterium (D-D) neutron generator for energy-selective transmission tomography
Soubelet, B., Adams, R., Kromer, H., Zboray, R., & Prasser, H. M. (2019). Feasibility study of using a compact deuterium-deuterium (D-D) neutron generator for energy-selective transmission tomography. Radiation Physics and Chemistry, 156, 292-299. https://doi.org/10.1016/j.radphyschem.2018.11.017
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
Corrective interface tracking approach to simulate finite-size bubbly flows
Badreddine, H., Lafferty, N., Ničeno, B., & Prasser, H. M. (2018). Corrective interface tracking approach to simulate finite-size bubbly flows. Chemical Engineering Science, 178, 61-69. https://doi.org/10.1016/j.ces.2017.12.028
Simulations of droplet merging with free surface and bubble column reactor with finite-size Lagrangian particle tracking
Badreddine, H., & Ničeno, B. (2018). Simulations of droplet merging with free surface and bubble column reactor with finite-size Lagrangian particle tracking. Chemical Engineering Science, 176, 609-621. https://doi.org/10.1016/j.ces.2017.10.037
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
PIV measurements in the vicinity of a steam sparger in the PANDA facility
Kapulla, R., Uong, D., Zimmer, C., & Paladino, D. (2018). PIV measurements in the vicinity of a steam sparger in the PANDA facility. Nuclear Engineering and Design, 336, 112-121. https://doi.org/10.1016/j.nucengdes.2017.07.003
Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell
Papadionysiou, M., Perret, G., Zboray, R., Adams, R., & Mosset, J. B. (2018). Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell. Nuclear Engineering and Design, 332, 119-126. https://doi.org/10.1016/j.nucengdes.2018.03.033
Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel
Qian, G., Niffenegger, M., Sharabi, M., & Lafferty, N. (2018). Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel. Fatigue and Fracture of Engineering Materials and Structures, 41(7), 1559-1575. https://doi.org/10.1111/ffe.12796
Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios
Rýdl, A., Fernandez-Moguel, L., & Lind, T. (2018). Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios. Nuclear Technology, 205(5), 655-670. https://doi.org/10.1080/00295450.2018.1511213
800 fps neutron radiography of air-water two-phase flow
Zboray, R., & Trtik, P. (2018). 800 fps neutron radiography of air-water two-phase flow. MethodsX, 5, 96-102. https://doi.org/10.1016/j.mex.2018.01.008
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
A Three-Dimensional, Immersed Boundary, Finite Volume Method for the Simulation of Incompressible Heat Transfer Flows around Complex Geometries
Badreddine, H., Sato, Y., Berger, M., & Ničeno, B. (2017). A Three-Dimensional, Immersed Boundary, Finite Volume Method for the Simulation of Incompressible Heat Transfer Flows around Complex Geometries. International Journal of Chemical Engineering, 2017, 1726519. https://doi.org/10.1155/2017/1726519
Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
Coindreau, O., Jäckel, B., Rocchi, F., Alcaro, F., Angelova, D., Bandini, G., … Zhabin, O. (2017). Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool. Presented at the 8th European review meeting on severe accident research (ERMSAR 2017). Warsaw, Poland.
A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity
Dehbi, A., Kalilainen, J., Lind, T., & Auvinen, A. (2017). A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity. Journal of Aerosol Science, 103, 67-82. https://doi.org/10.1016/j.jaerosci.2016.10.003
 

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