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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
Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques. Nuclear Technology. https://doi.org/10.1080/00295450.2019.1701906
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
Calculation of <em>λ</em> modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method
Morató, S., Bernal, Á., Miró, R., Roman, J. E., & Verdú, G. (2020). Calculation of λ modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method. Annals of Nuclear Energy, 137, 107077 (15 pp.). https://doi.org/10.1016/j.anucene.2019.107077
A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019
Rochman, D., Koning, A. J., & Sublet, J. C. (2020). A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019. Nuclear Data Sheets, 163, 163-190. https://doi.org/10.1016/j.nds.2019.12.003
Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics
Rochman, D., Dokhane, A., Vasiliev, A., Ferroukhi, H., & Hursin, M. (2020). Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics. European Physical Journal Plus, 135, 233 (18 pp.). https://doi.org/10.1140/epjp/s13360-020-00258-2
The OFFBEAT multi-dimensional fuel behavior solver
Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A. (2020). The OFFBEAT multi-dimensional fuel behavior solver. Nuclear Engineering and Design, 358, 110416 (16 pp.). https://doi.org/10.1016/j.nucengdes.2019.110416
Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
Siefman, D., Hursin, M., Perret, G., & Pautz, A. (2020). Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments. Progress in Nuclear Energy, 121, 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245
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
Measurement of the <sup>244</sup>Cm and <sup>246</sup>Cm neutron-induced cross sections at the n_TOF facility
Alcayne, V., Kimura, A., Mendoza, E., Cano-Ott, D., Aberle, O., Amaducci, S., … Žugec, P. (2019). Measurement of the 244Cm and 246Cm neutron-induced cross sections at the n_TOF facility. In J. E. García-Ramos, M. V. Andrés, F. Pérez-Bernal, J. A. Valera, & A. M. Moro (Eds.), Springer proceedings in physics: Vol. 225. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. https://doi.org/10.1007/978-3-030-22204-8_4
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
Characterization and first test of an i-TED prototype at CERN n_TOF
Babiano-Suarez, V., Caballero, L., Domingo-Pardo, C., Ladarescu, I., Aberle, O., Alcayne, V., … Žugec, P. (2019). Characterization and first test of an i-TED prototype at CERN n_TOF. In J. E. García-Ramos, M. V. Andrés, F. Pérez-Bernal, J. A. Valera, & A. M. Moro (Eds.), Springer proceedings in physics: Vol. 225. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. https://doi.org/10.1007/978-3-030-22204-8_18
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
 

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