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Bayesian Monte Carlo assimilation for the PETALE experimental programme using inter-dosimeter correlation
Laureau, A., Lamirand, V., Rochman, D., & Pautz, A. (2020). Bayesian Monte Carlo assimilation for the PETALE experimental programme using inter-dosimeter correlation. In Z. Ge, N. Shu, Y. Chen, W. Wang, & H. Zhang (Eds.), EPJ web of conferences: Vol. 239. ND 2019: international conference on nuclear data for science and technology (p. 18004 (4 pp.). https://doi.org/10.1051/epjconf/202023918004
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
An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor
Lamirand, V., Laureau, A., Rochman, D., Perret, G., Gruel, A., Leconte, P., … Pautz, A. (2019). An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor. In O. Serot & A. Chebboubi (Eds.), EPJ web of conferences: Vol. 211. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications (p. 03003 (5 pp.). https://doi.org/10.1051/epjconf/201921103003
Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor
Laureau, A., Lamirand, V., Rochman, D., & Pautz, A. (2019). Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor. In O. Serot & A. Chebboubi (Eds.), EPJ web of conferences: Vol. 211. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications (p. 03002 (5 pp.). https://doi.org/10.1051/epjconf/201921103002