Active Filters

  • (-) PSI Authors = Pautz, Andreas
Search Results 1 - 20 of 143

Pages

  • RSS Feed
Select Page
Piecewise linear interface-capturing volume-of-fluid method in axisymmetric cylindrical coordinates
Bureš, L., Sato, Y., & Pautz, A. (2021). Piecewise linear interface-capturing volume-of-fluid method in axisymmetric cylindrical coordinates. Journal of Computational Physics, 436, 110291 (36 pp.). https://doi.org/10.1016/j.jcp.2021.110291
Study of a current-based quench detection method for CCT magnets via a co-wound superconducting sensing wire
Gao, J., Auchmann, B., Hug, C., Pautz, A., & Sanfilippo, S. (2021). Study of a current-based quench detection method for CCT magnets via a co-wound superconducting sensing wire. IEEE Transactions on Applied Superconductivity, 31(5), 4701105 (5 pp.). https://doi.org/10.1109/TASC.2021.3059602
Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM
Radman, S., Fiorina, C., & Pautz, A. (2021). Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM. Nuclear Engineering and Design, 379, 111178 (13 pp.). https://doi.org/10.1016/j.nucengdes.2021.111178
Investigation on the effect of eccentricity for fuel disc irradiation tests
Scolaro, A., Van Uffelen, P., Fiorina, C., Schubert, A., Clifford, I., & Pautz, A. (2021). Investigation on the effect of eccentricity for fuel disc irradiation tests. Nuclear Engineering and Technology, 53(5), 1602-1611. https://doi.org/10.1016/j.net.2020.11.003
Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
Shama, A., Rochman, D., Pudollek, S., Caruso, S., & Pautz, A. (2021). Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules. Nuclear Engineering and Technology. https://doi.org/10.1016/j.net.2021.03.013
Development and verification of a methodology for neutron noise response to fuel assembly vibrations
Chionis, D., Dokhane, A., Belblidia, L., Ferroukhi, H., Girardin, G., & Pautz, A. (2020). Development and verification of a methodology for neutron noise response to fuel assembly vibrations. Annals of Nuclear Energy, 147, 107669 (15 pp.). https://doi.org/10.1016/j.anucene.2020.107669
Modeling of quench protection concepts for Canted-Cosine-Theta type high-field magnets
Gao, J., Auchmann, B., Brouwer, L., Pautz, A., & Sanfilippo, S. (2020). Modeling of quench protection concepts for Canted-Cosine-Theta type high-field magnets. IEEE Transactions on Applied Superconductivity, 30(4), 4701505 (5 pp.). https://doi.org/10.1109/TASC.2020.2974423
The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs
Hombourger, B., Křepel, J., & Pautz, A. (2020). The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs. Annals of Nuclear Energy, 144, 107504 (18 pp.). https://doi.org/10.1016/j.anucene.2020.107504
Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
Hursin, M., Rochman, D., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2020). Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5. In Proceedings of the PHYSOR 2020 (p. 1172 (10 pp.). Nuclear Energy Group.
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, 206(10), 1566-1583. https://doi.org/10.1080/00295450.2019.1701906
Validation of axial void profile measured by neutron noise techniques in CROCUS
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Validation of axial void profile measured by neutron noise techniques in CROCUS. In Proceedings of the PHYSOR 2020 (p. 1173 (8 pp.). Nuclear Energy Group.
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
Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
Lamirand, V., Rais, A., Pakari, O., Hursin, M., Laureau, A., Polhus, J., … Pautz, A. (2020). Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX. In Proceedings of the PHYSOR 2020 (p. 1573 (9 pp.). Nuclear Energy Group.
Uncertainty propagation based on correlated sampling technique for nuclear data applications
Laureau, A., Lamirand, V., Rochman, D., & Pautz, A. (2020). Uncertainty propagation based on correlated sampling technique for nuclear data applications. EPJ Nuclear Sciences and Technologies, 6, 8 (9 pp.). https://doi.org/10.1051/epjn/2020003
Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor
Laureau, A., Lamirand, V., Rochman, D., & Pautz, A. (2020). Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor. EPJ Nuclear Sciences and Technologies, 6, 9 (8 pp.). https://doi.org/10.1051/epjn/2020004
Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis
Mala, P., & Pautz, A. (2020). Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis. Nuclear Engineering and Technology, 52(11), 2431-2441. https://doi.org/10.1016/j.net.2020.04.022
Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics
Mala, P., Pautz, A., Ferroukhi, H., & Vasiliev, A. (2020). Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics. In Proceedings of the PHYSOR 2020 (p. 1583 (8 pp.). Nuclear Energy Group.
CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
Mylonakis, A. G., Demazière, C., Vinai, P., Lamirand, V., Rais, A., Pakari, O., … Pautz, A. (2020). CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements. In Proceedings of the PHYSOR 2020 (p. 1207 (9 pp.). Nuclear Energy Group.
Assessment of nTRACER and PARCS performance for VVER configurations
Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2020). Assessment of nTRACER and PARCS performance for VVER configurations. Nuclear Science and Engineering, 194(11), 1056-1066. https://doi.org/10.1080/00295639.2020.1753418
Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs
Papadionysiou, M., Kim, S., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Han, G. J. (2020). Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs. In Proceedings of the PHYSOR 2020 (p. 1285 (8 pp.). Nuclear Energy Group.
 

Pages