| Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
Stuckert, J., Steinbrueck, M., Kalilainen, J., Lind, T., & Birchley, J. (2021). Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release. Nuclear Engineering and Design, 379, 111267 (11 pp.). https://doi.org/10.1016/j.nucengdes.2021.111267 |
| 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 |
| Gas mixing caused by interacting heat sources PART I: experiments
Paranjape, S., Kapulla, R., Mignot, G., & Paladino, D. (2020). Gas mixing caused by interacting heat sources PART I: experiments. Nuclear Engineering and Design, 370, 110914 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110914 |
| 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-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., … 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., … 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 |
