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Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
Alhassan, E., Rochman, D., Sjöstrand, H., Vasiliev, A., Koning, A. J., & Ferroukhi, H. (2020). Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo. Annals of Nuclear Energy, 139, 107239 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107239
Treatment of the implicit effect in Shark-X
Hursin, M., Pelloni, S., Vasiliev, A., & Ferroukhi, H. (2020). Treatment of the implicit effect in Shark-X. Annals of Nuclear Energy, 138, 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178
Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
Kim, W., Hursin, M., Pautz, A., Vincent, L., Pavel, F., & Lee, D. (2020). Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor. Annals of Nuclear Energy, 136, 107034 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107034
On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
Siefman, D., Hursin, M., Aufiero, M., Bidaud, A., & Pautz, A. (2020). On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients. Annals of Nuclear Energy, 135, 106951 (13 pp.). https://doi.org/10.1016/j.anucene.2019.106951
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. Presented at the ICAPP 2019 - International congress on advances in nuclear power plants. Juan-les-pins, France.
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
Application of causality analysis on nuclear reactor systems
Chionis, D., Dokhane, A., Ferroukhi, H., & Pautz, A. (2019). Application of causality analysis on nuclear reactor systems. Chaos: An Interdisciplinary Journal of Nonlinear Science, 29(4), 043126 (16 pp.). https://doi.org/10.1063/1.5083905
Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
Clifford, I., Pecchia, M., Mukin, R., Cozzo, C., Ferroukhi, H., & Gorzel, A. (2019). Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs. Annals of Nuclear Energy, 130, 440-451. https://doi.org/10.1016/j.anucene.2019.03.017
The influence of thermal radiation on the free convection inside enclosures
Dehbi, A., Kelm, S., Kalilainen, J., & Mueller, H. (2019). The influence of thermal radiation on the free convection inside enclosures. Nuclear Engineering and Design, 341, 176-185. https://doi.org/10.1016/j.nucengdes.2018.10.025
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
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
Pool stratification and mixing induced by steam injection through spargers: CFD modelling of the PPOOLEX and PANDA experiments
Gallego-Marcos, I., Kudinov, P., Villanueva, W., Kapulla, R., Paranjape, S., Paladino, D., … Kotro, E. (2019). Pool stratification and mixing induced by steam injection through spargers: CFD modelling of the PPOOLEX and PANDA experiments. Nuclear Engineering and Design, 347, 67-85. https://doi.org/10.1016/j.nucengdes.2019.03.011
Impact of nuclear data uncertainty in the modeling of neutron-induced recoil atom energy distributions in silicon
Griffin, P. J., Koning, A. J., & Rochman, D. (2019). Impact of nuclear data uncertainty in the modeling of neutron-induced recoil atom energy distributions in silicon. IEEE Transactions on Nuclear Science, 66(7), 1719-1729. https://doi.org/10.1109/TNS.2019.2894730
Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part1: theory
Hennig, D., Lange, C., Rizwan-uddin,, Dokhane, A., & Knospe, A. (2019). Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part1: theory. Progress in Nuclear Energy, 115, 231-249. https://doi.org/10.1016/j.pnucene.2019.02.009
Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part2: application
Hennig, D., Rizwan-uddin,, Lange, C., Dokhane, A., & Knospe, A. (2019). Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part2: application. Progress in Nuclear Energy, 113, 263-280. https://doi.org/10.1016/j.pnucene.2019.01.009
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 1
Herranz, L. E., Pellegrini, M., Lind, T., Sonnenkalb, M., Godin-Jacqmin, L., López, C., … Sevon, T. (2019). Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 1. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2019). La Grange Park: American Nuclear Society (ANS).
Breed-and-burn fuel cycle in molten salt reactors
Hombourger, B., Křepel, J., & Pautz, A. (2019). Breed-and-burn fuel cycle in molten salt reactors. EPJ Nuclear Sciences and Technologies, 5, 15 (10 pp.). https://doi.org/10.1051/epjn/2019026
Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2019). Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique. Presented at the International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Portland, OR, USA: American Nuclear Society.
Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
Hursin, M., Park, J., Kim, W., Siefman, D., Perret, G., Vasiliev, A., … Lee, D. (2019). Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5. Presented at the International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Portland, OR, USA.
 

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