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Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
Betschart, T., Lind, T., & Prasser, H. M. (2020). Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions. Nuclear Engineering and Design, 366, 110768 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110768
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., Huhtanen, R., Kale, V., Kanaev, A., Kapulla, R., Kelm, S., Kim, J., Nishimura, T., Paladino, D., Paranjape, S., Schramm, B., Sharabi, M., Shen, F., Wei, B., … 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-18) (pp. 508-521). 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., Frybort, O., Melichar, T., Tarantino, M., Franke, S., Eckert, S., Class, A., Yanez, J., Grishchenko, D., Jeltsov, M., Kudinov, P., Roelofs, F., Zwijsen, K., Visser, D. C., … 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
Uncertainties in pressurized thermal shock analyses
Niffenegger, M., Garrido, O. C., Mora, D. F., Qian, G., Mukin, R., Sharabi, M., Lafferty, N., & Niceno, B. (2019). Uncertainties in pressurized thermal shock analyses. In PVP - American Society of Mechanical Engineers. Pressure vessels and piping division: Vol. 3. Design and analysis: 4th international symposium on coke drum life cycle management (pp. PVP2019-94076 (10 pp.). https://doi.org/10.1115/PVP2019-94076
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
Development of neutron and X-ray imaging techniques for nuclear fuel bundle optimization
Zboray, R., Bolesch, C., & Prasser, H. M. (2018). Development of neutron and X-ray imaging techniques for nuclear fuel bundle optimization. Nuclear Engineering and Design, 336, 24-33. https://doi.org/10.1016/j.nucengdes.2017.04.035
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
 

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