Query

Active Filters

  • (-) PSI Laboratories = Reactor Physics and Thermal-Hydraulics LRT
Search Results 1 - 20 of 639

Pages

  • CSV Spreadsheet
  • Excel Spreadsheet
  • RSS Feed
Select Page
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
Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
Andreani, M., Kapulla, R., Kelm, S., Paladino, D., & Paranjape, S. (2020). Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code. Journal of Nuclear Engineering and Radiation Science, 6(2), 021110 (18 pp.). https://doi.org/10.1115/1.4046296
Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies
Bernal, A., Pecchia, M., Rochman, D., Vasiliev, A., & Ferroukhi, H. (2020). Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies. In Proceedings of the PHYSOR 2020 (p. 1197 (8 pp.). Nuclear Energy Group.
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
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
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., Dykin, V., Por, G., Nylén, H., & 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
Validation of axial void profile measured by neutron noise techniques in CROCUS
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., Dykin, V., Por, G., Nylén, H., & 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.
Evaporation of materials from the molten salt reactor fuel under elevated temperatures
Kalilainen, J., Nichenko, S., & Krepel, J. (2020). Evaporation of materials from the molten salt reactor fuel under elevated temperatures. Journal of Nuclear Materials, 533, 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
Khvostov, G. (2020). Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code. Nuclear Engineering and Technology. https://doi.org/10.1016/j.net.2020.05.015
Analytical criteria for fuel fragmentation and burst FGR during a LOCA
Khvostov, G. (2020). Analytical criteria for fuel fragmentation and burst FGR during a LOCA. Nuclear Engineering and Technology, 52(10), 2402-2409. https://doi.org/10.1016/j.net.2020.03.009
Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code
Khvostov, G. (2020). Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code. Nuclear Engineering and Technology, 52(1), 135-147. https://doi.org/10.1016/j.net.2019.07.010
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., Paquee, U., Pohl, C., Hübner, S., Lange, C., Frajtag, P., Godat, D., Perret, G., Fioirina, C., & 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.
A summary of fission-product-transport phenomena during SGTR severe accidents
Lind, T., Campbell, S., Herranz, L. E., Kissane, M., & Song, J. H. (2020). A summary of fission-product-transport phenomena during SGTR severe accidents. Nuclear Engineering and Design, 363, 110635 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110635
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. 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.
Measurement of the <sup>154</sup>Gd(n,<em>γ</em>) cross section and its astrophysical implications
Mazzone, A., Cristallo, S., Aberle, O., Alaerts, G., Alcayne, V., Amaducci, S., Andrzejewski, J., Audouin, L., Babiano-Suarez, V., Bacak, M., Dressler, R., Heinitz, S., Kivel, N., Maugeri, E., Rochman, D., Schumann, D., Talip, Z., Ulrich, J., & Žugec, P. (2020). Measurement of the 154Gd(n,γ) cross section and its astrophysical implications. Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics, 804, 135405 (6 pp.). https://doi.org/10.1016/j.physletb.2020.135405
 

Pages