Active Filters

  • (-) PSI Authors = Fernandez Moguel, Leticia
Search Results 1 - 20 of 26
Select Page
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3
Lind, T., Pellegrini, M., Herranz, L. E., Sonnenkalb, M., Nishi, Y., Tamaki, H., … Sevon, T. (2021). Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3. Nuclear Engineering and Design, 376, 111138 (12 pp.). https://doi.org/10.1016/j.nucengdes.2021.111138
Modelling of fission products release in VERDON-1 experiment with cGEMS: coupling of severe accident code MELCOR with GEMS thermodynamic modelling package
Nichenko, S., Kalilainen, J., Fernandez Moguel, L., & Lind, T. (2021). Modelling of fission products release in VERDON-1 experiment with cGEMS: coupling of severe accident code MELCOR with GEMS thermodynamic modelling package. Annals of Nuclear Energy, 152, 107972 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107972
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), phase 2 - results of severe accident analyses for unit 2
Sonnenkalb, M., Pellegrini, M., Herranz, L. E., Lind, T., Morreale, A. C., Kanda, K., … Sevon, T. (2020). Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), phase 2 - results of severe accident analyses for unit 2. Nuclear Engineering and Design, 369, 110840 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110840
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-18) (pp. 508-521). 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
Application of a newly developed computer code model for nitriding and re-oxidation of cladding materials on separate effect tests and integral experiments
Jäckel, B. S., Lind, T., Fernandez-Moguel, L., Steinbrück, M., & Park, S. (2019). Application of a newly developed computer code model for nitriding and re-oxidation of cladding materials on separate effect tests and integral experiments. In Proceedings of the ERMSAR 2019 (p. 024 (14 pp.). sine nomine.
Overwiew 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 3
Lind, T., Pellegrini, M., Herranz, L. E., Sonnenkalb, M., Nishi, Y., Tamaki, H., … Sevon, T. (2019). Overwiew 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 3. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18) (pp. 1133-1146). American Nuclear Society (ANS).
Development of a computer code model for nitriding and re‐oxidation of cladding materials under severe accident conditions
Jäckel, B. S., Lind, T., Fernandez-Moguel, L., Steinbrück, M., & Park, S. (2018). Development of a computer code model for nitriding and re‐oxidation of cladding materials under severe accident conditions. In Proceedings of the international conference nuclear energy for New Europe (NENE 2018) (p. 506.1 (8 pp.). Nuclear Society of Slovenia.
Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios
Rýdl, A., Fernandez-Moguel, L., & Lind, T. (2018). Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios. Nuclear Technology, 205(5), 655-670. https://doi.org/10.1080/00295450.2018.1511213
Modeling of fission roduct scrubbing in experiments and in integral severe accident scenarios
Rýdl, A., Lind, T., & Fernandez-Moguel, L. (2017). Modeling of fission roduct scrubbing in experiments and in integral severe accident scenarios (p. 308 (14 pp.). Presented at the 8th European review meeting on severe accident research (ERMSAR 2017). .
Cladding oxidation during air ingress. Part II: synthesis of modelling results
Beuzet, E., Haurais, F., Bals, C., Coindreau, O., Fernandez-Moguel, L., Vasiliev, A., & Park, S. (2016). Cladding oxidation during air ingress. Part II: synthesis of modelling results. Annals of Nuclear Energy, 93, 18-27. https://doi.org/10.1016/j.anucene.2015.12.031
Benchmark study of the accident at the Fukushima Daiichi NPS: best-estimate case comparison
Pellegrini, M., Dolganov, K., Herranz, L. E., Bonneville, H., Luxat, D., Sonnenkalb, M., … Nishi, Y. (2016). Benchmark study of the accident at the Fukushima Daiichi NPS: best-estimate case comparison. Nuclear Technology, 196(2), 198-210. https://doi.org/10.13182/NT16-63
Impact of containment venting on source term for Fukushima-like BWR scenarios
Rýdl, A., Fernandez-Moguel, L., & Lind, T. (2016). Impact of containment venting on source term for Fukushima-like BWR scenarios (p. N11P1234 (13 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
Analysis of Fukushima Daiichi NPP unit 3 with Melcor_2.1
Fernandez-Moguel, L., Rydl, A., & Jaeckel, B. (2015). Analysis of Fukushima Daiichi NPP unit 3 with Melcor_2.1. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 6401-6411). American Nuclear Society.
Analysis of the accident in the Fukushima Daiichi nuclear power station unit 3 with MELCOR_2.1
Fernandez-Moguel, L., & Birchley, J. (2015). Analysis of the accident in the Fukushima Daiichi nuclear power station unit 3 with MELCOR_2.1. Annals of Nuclear Energy, 83, 193-215. https://doi.org/10.1016/j.anucene.2015.04.021
Comparative assessment of PSI air oxidation model implementation in SCDAPSim3.5, MELCOR 1.8.6 and MELCOR 2.1
Fernandez-Moguel, L. (2015). Comparative assessment of PSI air oxidation model implementation in SCDAPSim3.5, MELCOR 1.8.6 and MELCOR 2.1. Annals of Nuclear Energy, 81, 134-142. https://doi.org/10.1016/j.anucene.2015.03.015
Effect of nitriding during an air ingress scenario
Park, S., Fernandez-Moguel, L., Prasser, H. M., Birchley, J., Steinbrück, M., & Seifert, H. J. (2015). Effect of nitriding during an air ingress scenario. In TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 2 (pp. 380-390). European Nuclear Society.
SARNET2 benchmark on air ingress experiments QUENCH-10, -16
Fernandez-Moguel, L., Bals, C., Beuzet, E., Bratfisch, C., Coindreau, O., Hózer, Z., … Vryashkova, P. (2014). SARNET2 benchmark on air ingress experiments QUENCH-10, -16. Annals of Nuclear Energy, 74, 12-23. https://doi.org/10.1016/j.anucene.2014.05.013
Spent fuel pool under severe accident conditions
Jaeckel, B., Birchley, J., & Fernandez-Moguel, L. (2014). Spent fuel pool under severe accident conditions. In Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22) (p. V003T06A029 (7 pp.). https://doi.org/10.1115/ICONE22-30729