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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
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
On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology
Alhassan, E., Sjöstrand, H., Helgesson, P., Österlund, M., Pomp, S., Koning, A. J., & Rochman, D. (2016). On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology. Progress in Nuclear Energy, 88, 43-52. https://doi.org/10.1016/j.pnucene.2015.11.015
Post irradiation examination of nuclear fuel: toward a complete analysis
Degueldre, C., Bertsch, J., & Martin, M. (2016). Post irradiation examination of nuclear fuel: toward a complete analysis. Progress in Nuclear Energy, 92, 242-253. https://doi.org/10.1016/j.pnucene.2016.03.025
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe – Part II: thorium fuel cycle
Lindley, B. A., Fiorina, C., Gregg, R., Franceschini, F., & Parks, G. T. (2016). The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe – Part II: thorium fuel cycle. Progress in Nuclear Energy, 87, 144-155. https://doi.org/10.1016/j.pnucene.2014.11.016
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe - part I: uranium fuel cycle
Lindley, B. A., Fiorina, C., Gregg, R., Franceschini, F., & Parks, G. T. (2015). The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe - part I: uranium fuel cycle. Progress in Nuclear Energy, 85, 498-510. https://doi.org/10.1016/j.pnucene.2015.07.020
Core neutronics characterization of the GFR2400 gas cooled fast reactor
Perkó, Z., Pelloni, S., Mikityuk, K., Křepel, J., Szieberth, M., Gaëtan, G., … Poette, C. (2015). Core neutronics characterization of the GFR2400 gas cooled fast reactor. Progress in Nuclear Energy, 83, 460-481. https://doi.org/10.1016/j.pnucene.2014.09.016
Multi-scale approach to advanced fuel modelling for enhanced safety
Ribeiro, F., & Khvostov, G. (2015). Multi-scale approach to advanced fuel modelling for enhanced safety. Progress in Nuclear Energy, 84, 24-35. https://doi.org/10.1016/j.pnucene.2015.03.022
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics
Zanetti, M., Cammi, A., Fiorina, C., & Luzzi, L. (2015). A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics. Progress in Nuclear Energy, 83, 82-98. https://doi.org/10.1016/j.pnucene.2015.02.014
X-ray absorption in plutonium uranium mixed oxide fuel: Thorium characterization
Cozzo, C., Orlov, A., Borca, C., & Degueldre, C. (2014). X-ray absorption in plutonium uranium mixed oxide fuel: Thorium characterization. Progress in Nuclear Energy, 72, 91-95. https://doi.org/10.1016/j.pnucene.2013.09.009
Electron energy loss spectroscopy investigations through nano-ablated actinide dioxide samples
Degueldre, C., & Veleva, L. (2014). Electron energy loss spectroscopy investigations through nano-ablated actinide dioxide samples. Progress in Nuclear Energy, 72, 96-100. https://doi.org/10.1016/j.pnucene.2013.11.016
The first symposium on the scientific basis of the nuclear fuel cycle symposium e @ EMRS 13 editorial note
Degueldre, C., Grimes, R., Rondinella, V., Poinssot, C., & Bosbach, D. (2014). The first symposium on the scientific basis of the nuclear fuel cycle symposium e @ EMRS 13 editorial note. Progress in Nuclear Energy, 72, 1-2. https://doi.org/10.1016/j.pnucene.2014.02.017