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Nitriding model for zirconium based fuel cladding in severe accident codes
Jäckel, B. S., Birchley, J. C., Lind, T., Steinbrück, M., & Park, S. (2023). Nitriding model for zirconium based fuel cladding in severe accident codes. Journal of Nuclear Materials, 582, 154466 (7 pp.). https://doi.org/10.1016/j.jnucmat.2023.154466
Current understanding of high-temperature oxidation phenomena during air ingress scenarios
Park, S., Lind, T., Birchley, J., & Steinbrueck, M. (2022). Current understanding of high-temperature oxidation phenomena during air ingress scenarios. In F. Gabrielli, L. E. Herranz, & S. Paci (Eds.), Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident (p. 284 (10 pp.). Karlsruher Institut für Technologie (KIT).
Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
Stuckert, J., Steinbrueck, M., Kalilainen, J., Lind, T., & Birchley, J. (2021). Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release. Nuclear Engineering and Design, 379, 111267 (11 pp.). https://doi.org/10.1016/j.nucengdes.2021.111267
Integral analyses of fission product retention at mitigated thermally-induced SGTR using ARTIST experimental data
Rýdl, A., Lind, T., & Birchley, J. (2016). Integral analyses of fission product retention at mitigated thermally-induced SGTR using ARTIST experimental data. Nuclear Engineering and Design, 297, 175-187. https://doi.org/10.1016/j.nucengdes.2015.11.014
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
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.
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
Long-term SBO with selected mitigative measures: MELCOR parametric calculations for a 2-loop PWR
Rydl, A., Jaeckel, B., Birchley, J. C., & Lind, T. (2014). Long-term SBO with selected mitigative measures: MELCOR parametric calculations for a 2-loop PWR. In Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22) (p. V006T15A012 (10 pp.). https://doi.org/10.1115/ICONE22-30351
Significance of Phébus-FP results for plant safety in Switzerland
Birchley, J., & Güntay, S. (2013). Significance of Phébus-FP results for plant safety in Switzerland. Annals of Nuclear Energy, 61, 206-214. https://doi.org/10.1016/j.anucene.2013.02.032
Analysis of QUENCH-10 and -16 air ingress experiments with SCDAPSim3.5
Fernandez-Moguel, L., & Birchley, J. (2013). Analysis of QUENCH-10 and -16 air ingress experiments with SCDAPSim3.5. Annals of Nuclear Energy, 53, 202-212. https://doi.org/10.1016/j.anucene.2012.08.030
Simulation of air oxidation during a reactor accident sequence: part 1 - phenomenology and model development
Birchley, J., & Fernandez-Moguel, L. (2012). Simulation of air oxidation during a reactor accident sequence: part 1 - phenomenology and model development. Annals of Nuclear Energy, 40(1), 163-170. https://doi.org/10.1016/j.anucene.2011.10.019
Simulation of air oxidation during a reactor accident sequence: part 2 - analysis of PARAMETER-SF4 air ingress experiment using RELAP5/SCDAPSIM
Fernandez-Moguel, L., & Birchley, J. (2012). Simulation of air oxidation during a reactor accident sequence: part 2 - analysis of PARAMETER-SF4 air ingress experiment using RELAP5/SCDAPSIM. Annals of Nuclear Energy, 40(1), 141-152. https://doi.org/10.1016/j.anucene.2011.10.018
Assessment of SCDAP/RELAP5 modelling of top-down reflood, using PARAMETER bundle experiments
Birchley, J., & Fernandez Moguel, L. (2011). Assessment of SCDAP/RELAP5 modelling of top-down reflood, using PARAMETER bundle experiments. In Proceedings of ICAPP 2011 (pp. 1476-1485).
Planning support and preliminary post-test analysis of QUENCH-L0 using SCDAP/RELAP and SCDAP/Sim
Fernandez Moguel, L., & Birchley, J. (2011). Planning support and preliminary post-test analysis of QUENCH-L0 using SCDAP/RELAP and SCDAP/Sim. In Proceedings of ICAPP 2011 (pp. 1162-1170).
Analyses of the Phébus FPT3 experiment using the severe accident codes ATHLET-CD, ICARE/CATHARE, and MELCOR
Repetto, G., de Luze, O., Drath, T., Koch, M. K., Hollands, T., Trambauer, K., … Birchley, J. (2011). Analyses of the Phébus FPT3 experiment using the severe accident codes ATHLET-CD, ICARE/CATHARE, and MELCOR. Nuclear Technology, 176(3), 352-371. https://doi.org/10.13182/NT11-A13313
Experimental and calculation results of the integral reflood test QUENCH-15 with ZIRLO<sup>TM </sup>cladding tubes in comparison with results of previous QUENCH tests
Stuckert, J., Birchley, J., Große, M., Jaeckel, B., & Steinbrück, M. (2011). Experimental and calculation results of the integral reflood test QUENCH-15 with ZIRLOTM cladding tubes in comparison with results of previous QUENCH tests. Nuclear Engineering and Design, 241(8), 3224-3233. https://doi.org/10.1016/j.nucengdes.2011.05.004
Analysis of QUENCH-ACM experiments using SCDAP/RELAP5
Birchley, J., & Stuckert, J. (2010). Analysis of QUENCH-ACM experiments using SCDAP/RELAP5. In International congress on advances in nuclear power plants 2010, ICAPP 2010: Vol. 2. Proceedings of ICAPP '10 (pp. 941-950). American Nuclear Society.
Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
Dubourg, R., Austregesilo, H., Bals, C., Barrachin, M., Birchley, J., Haste, T., … Vimi, A. (2010). Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences. Progress in Nuclear Energy, 52(1), 97-108. https://doi.org/10.1016/j.pnucene.2009.09.012
Accident management following loss-of-coolant accidents during cooldown in a Westinghouse two-loop PWR
Haste, T. J., Birchley, J., & Richner, M. (2010). Accident management following loss-of-coolant accidents during cooldown in a Westinghouse two-loop PWR. Nuclear Engineering and Design, 240(6), 1599-1605. https://doi.org/10.1016/j.nucengdes.2010.02.006
B<sub>4</sub>C oxidation modelling in severe accident codes: applications to PHEBUS and QUENCH experiments
Repetto, G., De Luze, O., Seiler, N., Trambauer, K., Austregesilo, H., Birchley, J., … Hollands, T. (2010). B4C oxidation modelling in severe accident codes: applications to PHEBUS and QUENCH experiments. Progress in Nuclear Energy, 52(1), 37-45. https://doi.org/10.1016/j.pnucene.2009.09.017