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Towards establishment of an efficient approach for validation of PWR full core Monte Carlo simulations at hot zero power conditions
Berry, L., Vasiliev, A., Hursin, M., Rochman, D., Frankl, M., & Ferroukhi, H. (2024). Towards establishment of an efficient approach for validation of PWR full core Monte Carlo simulations at hot zero power conditions. Progress in Nuclear Energy, 172, 105203 (16 pp.). https://doi.org/10.1016/j.pnucene.2024.105203
Preliminary safety analysis of the TRANSMUTEX sub-critical reactor using the GeN-Foam multi-physics solver
Guilbaud, T., Fiorina, C., Pautz, A., & Carminati, F. (2024). Preliminary safety analysis of the TRANSMUTEX sub-critical reactor using the GeN-Foam multi-physics solver. Progress in Nuclear Energy, 168, 104980 (10 pp.). https://doi.org/10.1016/j.pnucene.2023.104980
Influence of solid electrolyte material selection on electromotive force characteristics of oxygen sensor for lead-cooled fast reactor
Tu, X., Zhu, H., Wu, W., Wang, X., Guo, Z., Wang, T., … Liu, F. (2024). Influence of solid electrolyte material selection on electromotive force characteristics of oxygen sensor for lead-cooled fast reactor. Progress in Nuclear Energy, 176, 105368 (12 pp.). https://doi.org/10.1016/j.pnucene.2024.105368
Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1
Malicki, M., & Lind, T. (2023). Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1. Progress in Nuclear Energy, 158, 104609 (15 pp.). https://doi.org/10.1016/j.pnucene.2023.104609
Parametric study highlighting cooler and spray activation on the transient mixing of a three-gas composition in the PANDA facility
Paladino, D., Paranjape, S., Mignot, G., & Kapulla, R. (2022). Parametric study highlighting cooler and spray activation on the transient mixing of a three-gas composition in the PANDA facility. Progress in Nuclear Energy, 150, 104283 (9 pp.). https://doi.org/10.1016/j.pnucene.2022.104283
Towards coupling conventional with high-fidelity fuel behavior analysis tools
Scolaro, A., Van Uffelen, P., Schubert, A., Fiorina, C., Brunetto, E., Clifford, I., & Pautz, A. (2022). Towards coupling conventional with high-fidelity fuel behavior analysis tools. Progress in Nuclear Energy, 152, 104357 (12 pp.). https://doi.org/10.1016/j.pnucene.2022.104357
Radiological characterisation in view of nuclear reactor decommissioning: on-site benchmarking exercise of a biological shield
Herranz, M., Boden, S., Völgyesi, P., Idoeta, R., Broeckx, W., Ruiz González, J., … Legarda, F. (2021). Radiological characterisation in view of nuclear reactor decommissioning: on-site benchmarking exercise of a biological shield. Progress in Nuclear Energy, 137, 103740 (13 pp.). https://doi.org/10.1016/j.pnucene.2021.103740
Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise
Pázsit, I., Torres, L. A., Hursin, M., Nylén, H., Dykin, V., & Montalvo, C. (2021). Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise. Progress in Nuclear Energy, 138, 103805 (11 pp.). https://doi.org/10.1016/j.pnucene.2021.103805
Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM
Skolik, K., Allison, C., Hohorst, J., Malicki, M., Perez-Ferragut, M., Pieńkowski, L., & Trivedi, A. (2021). Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM. Progress in Nuclear Energy, 134, 103648 (15 pp.). https://doi.org/10.1016/j.pnucene.2021.103648
Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
Siefman, D., Hursin, M., Perret, G., & Pautz, A. (2020). Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments. Progress in Nuclear Energy, 121, 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245
Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part1: theory
Hennig, D., Lange, C., Rizwan-uddin, Dokhane, A., & Knospe, A. (2019). Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part1: theory. Progress in Nuclear Energy, 115, 231-249. https://doi.org/10.1016/j.pnucene.2019.02.009
Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part2: application
Hennig, D., Rizwan-uddin, Lange, C., Dokhane, A., & Knospe, A. (2019). Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part2: application. Progress in Nuclear Energy, 113, 263-280. https://doi.org/10.1016/j.pnucene.2019.01.009
Study of level swell for a Filtered Containment Venting System at the VEFITA facility
Yang, J., Suckow, D., Lind, T., & Prasser, H. M. (2019). Study of level swell for a Filtered Containment Venting System at the VEFITA facility. Progress in Nuclear Energy, 113, 7-17. https://doi.org/10.1016/j.pnucene.2019.01.003
SiC cladding thermal conductivity requirements for normal operation and LOCA conditions
Cozzo, C., & Rahman, S. (2018). SiC cladding thermal conductivity requirements for normal operation and LOCA conditions. Progress in Nuclear Energy, 106, 278-283. https://doi.org/10.1016/j.pnucene.2018.03.016
Measurement of tungsten reactivity worth on VENUS-II light water reactor and validation of evaluated nuclear data
Jiang, W., Gu, L., Zhou, Q., Zhu, Q. F., Chen, L., Liu, X. Q., … Dai, Y. (2018). Measurement of tungsten reactivity worth on VENUS-II light water reactor and validation of evaluated nuclear data. Progress in Nuclear Energy, 108, 81-88. https://doi.org/10.1016/j.pnucene.2018.05.002
Analysis of the U L<sub>3</sub>-edge X-ray absorption spectra in UO<sub>2</sub> using molecular dynamics simulations
Bocharov, D., Chollet, M., Krack, M., Bertsch, J., Grolimund, D., Martin, M., … Kotomin, E. (2017). Analysis of the U L3-edge X-ray absorption spectra in UO2 using molecular dynamics simulations. Progress in Nuclear Energy, 94, 187-193. https://doi.org/10.1016/j.pnucene.2016.07.017
Uranium as a renewable for nuclear energy
Degueldre, C. (2017). Uranium as a renewable for nuclear energy. Progress in Nuclear Energy, 94, 174-186. https://doi.org/10.1016/j.pnucene.2016.03.031
Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
Grimm, P., Hursin, M., Perret, G., Siefman, D., & Ferroukhi, H. (2017). Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model. Progress in Nuclear Energy, 101, 280-287. https://doi.org/10.1016/j.pnucene.2017.03.018
Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances
Helgesson, P., Sjöstrand, H., Koning, A. J., Rydén, J., Rochman, D., Alhassan, E., & Pomp, S. (2017). Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances. Progress in Nuclear Energy, 96, 76-96. https://doi.org/10.1016/j.pnucene.2016.11.006
Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly
Leray, O., Fiorito, L., Rochman, D., Ferroukhi, H., Stankovskiy, A., & Van den Eynde, G. (2017). Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly. Progress in Nuclear Energy, 101, 486-495. https://doi.org/10.1016/j.pnucene.2017.05.033