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Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - part I: methodology demonstration
Di Nora, V. A., Fridman, E., Nikitin, E., Bilodid, Y., & Mikityuk, K. (2021). Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - part I: methodology demonstration. Annals of Nuclear Energy, 155, 108183 (9 pp.). https://doi.org/10.1016/j.anucene.2021.108183
Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data
Jiang, W., Gu, L., Zhu, Q. F., Zhou, Q., Ma, F., Zhang, L., … Chen, L. (2021). Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data. Annals of Nuclear Energy, 154, 108106 (8 pp.). https://doi.org/10.1016/j.anucene.2020.108106
Genetic algorithm based temperature control of the dense granular spallation target in China initiative accelerator driven system
Li, J. Y., Dai, Y., Gu, L., Zhang, Y. P., He, Z. Y., Xu, H. S., … Wang, D. W. (2021). Genetic algorithm based temperature control of the dense granular spallation target in China initiative accelerator driven system. Annals of Nuclear Energy, 154, 108127 (8 pp.). https://doi.org/10.1016/j.anucene.2021.108127
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
Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat
Rochman, D., Vasiliev, A., Ferroukhi, H., & Hursin, M. (2021). Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat. Annals of Nuclear Energy, 160, 108359 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108359
Development and application of marginal likelihood optimization for integral parameter adjustment
Siefman, D., Hursin, M., Schnabel, G., & Sjöstrand, H. (2021). Development and application of marginal likelihood optimization for integral parameter adjustment. Annals of Nuclear Energy, 159, 108255 (10 pp.). https://doi.org/10.1016/j.anucene.2021.108255
Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs
Verma, V., Chionis, D., Dokhane, A., & Ferroukhi, H. (2021). Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs. Annals of Nuclear Energy, 157, 108212 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108212
Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor
Ványi, A. S., Babcsány, B., Böröczki, Z. I., Horváth, A., Hursin, M., Szieberth, M., & Czifrus, S. (2021). Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor. Annals of Nuclear Energy, 155, 108144 (15 pp.). https://doi.org/10.1016/j.anucene.2021.108144
Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
Alhassan, E., Rochman, D., Sjöstrand, H., Vasiliev, A., Koning, A. J., & Ferroukhi, H. (2020). Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo. Annals of Nuclear Energy, 139, 107239 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107239
Development and verification of a methodology for neutron noise response to fuel assembly vibrations
Chionis, D., Dokhane, A., Belblidia, L., Ferroukhi, H., Girardin, G., & Pautz, A. (2020). Development and verification of a methodology for neutron noise response to fuel assembly vibrations. Annals of Nuclear Energy, 147, 107669 (15 pp.). https://doi.org/10.1016/j.anucene.2020.107669
The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs
Hombourger, B., Křepel, J., & Pautz, A. (2020). The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs. Annals of Nuclear Energy, 144, 107504 (18 pp.). https://doi.org/10.1016/j.anucene.2020.107504
Treatment of the implicit effect in Shark-X
Hursin, M., Pelloni, S., Vasiliev, A., & Ferroukhi, H. (2020). Treatment of the implicit effect in Shark-X. Annals of Nuclear Energy, 138, 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178
Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
Kim, W., Hursin, M., Pautz, A., Vincent, L., Pavel, F., & Lee, D. (2020). Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor. Annals of Nuclear Energy, 136, 107034 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107034
Calculation of <em>λ</em> modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method
Morató, S., Bernal, Á., Miró, R., Roman, J. E., & Verdú, G. (2020). Calculation of λ modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method. Annals of Nuclear Energy, 137, 107077 (15 pp.). https://doi.org/10.1016/j.anucene.2019.107077
Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method
Pelloni, S., & Rochman, D. (2020). Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method. Annals of Nuclear Energy, 145, 107509 (9 pp.). https://doi.org/10.1016/j.anucene.2020.107509
Improvement of PIE analysis with a full core simulation: the U1 case<br />  
Rochman, D., Vasiliev, A., Ferroukhi, H., Seidl, M., & Basualdo, J. (2020). Improvement of PIE analysis with a full core simulation: the U1 case
 . Annals of Nuclear Energy, 148, 107706 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107706
Nuclear data uncertainties for core parameters based on Swiss BWR operated cycles
Rochman, D., Dokhane, A., Vasiliev, A., Ferroukhi, H., & Hursin, M. (2020). Nuclear data uncertainties for core parameters based on Swiss BWR operated cycles. Annals of Nuclear Energy, 148, 107727 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107727
Optimization of Swiss used nuclear fuel canister for final repository: homogeneous vs. mixed loading
Rochman, D., Vasiliev, A., Ferroukhi, H., & Pecchia, M. (2020). Optimization of Swiss used nuclear fuel canister for final repository: homogeneous vs. mixed loading. Annals of Nuclear Energy, 148, 107756 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107756
On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
Siefman, D., Hursin, M., Aufiero, M., Bidaud, A., & Pautz, A. (2020). On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients. Annals of Nuclear Energy, 135, 106951 (13 pp.). https://doi.org/10.1016/j.anucene.2019.106951
Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors
Tiberga, M., de Oliveira, R. G. G., Cervi, E., Blanco, J. A., Lorenzi, S., Aufiero, M., … Rubiolo, P. (2020). Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors. Annals of Nuclear Energy, 142, 107428 (19 pp.). https://doi.org/10.1016/j.anucene.2020.107428
 

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