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TENDL-based evaluation and adjustment of p+<sup>111</sup>Cd between 1 and 100 MeV
Alhassan, E., Rochman, D., Vasiliev, A., Koning, A. J., & Ferroukhi, H. (2023). TENDL-based evaluation and adjustment of p+111Cd between 1 and 100 MeV. Applied Radiation and Isotopes, 198, 110832 (15 pp.). https://doi.org/10.1016/j.apradiso.2023.110832
Assessment of the influence of scaling on turbulent mixing in downcomer and core-inlet flow distribution
Fogliatto, E., Puragliesi, R., Clifford, I., & Ferroukhi, H. (2023). Assessment of the influence of scaling on turbulent mixing in downcomer and core-inlet flow distribution. Annals of Nuclear Energy, 185, 109715 (15 pp.). https://doi.org/10.1016/j.anucene.2023.109715
Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – overview and first results
Gupta, S., Herranz, L. E., Lebel, L. S., Sonnenkalb, M., Pellegrini, M., Marchetto, C., … Kärkelä, T. (2023). Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – overview and first results. Nuclear Engineering and Design, 404, 112189 (20 pp.). https://doi.org/10.1016/j.nucengdes.2023.112189
Determination of the hydrogen heat of transport in Zircaloy-4
Kang, S., Huang, P. H., Petrov, V., Manera, A., Ahn, T., Kammenzind, B., & Motta, A. T. (2023). Determination of the hydrogen heat of transport in Zircaloy-4. Journal of Nuclear Materials, 573, 154122 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.154122
Validation of RANS-based turbulence models against high-resolution experiments and DNS for buoyancy-driven flow with stratified fronts
Mao, J., Vishwakarma, V., Welker, Z., Tai, C. K., Bolotnov, I. A., Petrov, V., & Manera, A. (2023). Validation of RANS-based turbulence models against high-resolution experiments and DNS for buoyancy-driven flow with stratified fronts. Nuclear Science and Engineering. https://doi.org/10.1080/00295639.2023.2241800
Current status of MELCOR 2.2 for fusion safety analyses
Mascari, F., Bersano, A., Adorni, M., D'Ovidio, G., Martín-Fuertes, F., Jin, X. Z., … Malicki, M. (2023). Current status of MELCOR 2.2 for fusion safety analyses. Fusion Engineering and Design, 194, 113869 (7 pp.). https://doi.org/10.1016/j.fusengdes.2023.113869
LTO modifications to reduce the pts issue - results of TH calculations in the context of the APAL European project
Puustinen, M., Patel, G., Kral, P., Nikl, T., Clifford, I., Trewin, R., … Vyshemirskyi, M. (2023). LTO modifications to reduce the pts issue - results of TH calculations in the context of the APAL European project. In Proceedings 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 282-295). https://doi.org/10.13182/NURETH20-40206
Evaluation of uncertainties in thermal-hydraulic analyses of PTS for the APAL European project
Trewin, R., Prošek, A., Kral, P., Clifford, I., Perret, G., Hartung, J., … Filonova, Y. (2023). Evaluation of uncertainties in thermal-hydraulic analyses of PTS for the APAL European project. In Proceedings of the 20th international topical meeting on nuclear reactor thermal hydraulics (pp. 5791-5805). https://doi.org/10.13182/NURETH20-40288
The scaling effect analysis of counterpart test between LSTF and ATLAS IET facilities on 1% top head break LOCA
Alyammahi, N., Yoon, H. J., Al-Yahia, O. S., & Leung, R. (2022). The scaling effect analysis of counterpart test between LSTF and ATLAS IET facilities on 1% top head break LOCA. Nuclear Engineering and Design, 397, 111917 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.111917
Validation of RELAP5 MOD3.3 for 1% reactor pressure vessel top head break loss of coolant accident via the ATLAS facility
Yoon, H. J., Alyammahi, N., Al-Yahia, O. S., & Leung, R. (2022). Validation of RELAP5 MOD3.3 for 1% reactor pressure vessel top head break loss of coolant accident via the ATLAS facility. Nuclear Engineering and Design, 400, 112054 (14 pp.). https://doi.org/10.1016/j.nucengdes.2022.112054