| Current understanding of high-temperature oxidation phenomena during air ingress scenarios
Park, S., Lind, T., Birchley, J., & Steinbrueck, M. (2022). Current understanding of high-temperature oxidation phenomena during air ingress scenarios. In F. Gabrielli, L. E. Herranz, & S. Paci (Eds.), Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident (p. 284 (10 pp.). Karlsruher Institut für Technologie (KIT). |
| 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 |
| Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis
Fernandez-Moguel, L., Rydl, A., & Lind, T. (2019). Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis. Annals of Nuclear Energy, 123, 59-77. https://doi.org/10.1016/j.anucene.2018.09.008 |
| 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 |
| A summary of the ARTIST: aerosol retention during SGTR severe accident
Lind, T., Guentay, S., Herranz, L. E., & Suckow, D. (2019). A summary of the ARTIST: aerosol retention during SGTR severe accident. Annals of Nuclear Energy, 131, 385-400. https://doi.org/10.1016/j.anucene.2019.04.006 |
| 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 |
| Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario
Paranjape, S., Mignot, G., Kapulla, R., & Paladino, D. (2019). Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario. Nuclear Engineering and Design, 342, 88-98. https://doi.org/10.1016/j.nucengdes.2018.11.017 |
| 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 |
