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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
Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques. Nuclear Technology. https://doi.org/10.1080/00295450.2019.1701906
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
A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019
Rochman, D., Koning, A. J., & Sublet, J. C. (2020). A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019. Nuclear Data Sheets, 163, 163-190. https://doi.org/10.1016/j.nds.2019.12.003
Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics
Rochman, D., Dokhane, A., Vasiliev, A., Ferroukhi, H., & Hursin, M. (2020). Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics. European Physical Journal Plus, 135, 233 (18 pp.). https://doi.org/10.1140/epjp/s13360-020-00258-2
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
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
Measurement of the <sup>244</sup>Cm and <sup>246</sup>Cm neutron-induced cross sections at the n_TOF facility
Alcayne, V., Kimura, A., Mendoza, E., Cano-Ott, D., Aberle, O., Amaducci, S., … Žugec, P. (2019). Measurement of the 244Cm and 246Cm neutron-induced cross sections at the n_TOF facility. In J. E. García-Ramos, M. V. Andrés, F. Pérez-Bernal, J. A. Valera, & A. M. Moro (Eds.), Springer proceedings in physics: Vol. 225. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. https://doi.org/10.1007/978-3-030-22204-8_4
Characterization and first test of an i-TED prototype at CERN n_TOF
Babiano-Suarez, V., Caballero, L., Domingo-Pardo, C., Ladarescu, I., Aberle, O., Alcayne, V., … Žugec, P. (2019). Characterization and first test of an i-TED prototype at CERN n_TOF. In J. E. García-Ramos, M. V. Andrés, F. Pérez-Bernal, J. A. Valera, & A. M. Moro (Eds.), Springer proceedings in physics: Vol. 225. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. https://doi.org/10.1007/978-3-030-22204-8_18
Application of causality analysis on nuclear reactor systems
Chionis, D., Dokhane, A., Ferroukhi, H., & Pautz, A. (2019). Application of causality analysis on nuclear reactor systems. Chaos: An Interdisciplinary Journal of Nonlinear Science, 29(4), 043126 (16 pp.). https://doi.org/10.1063/1.5083905
Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
Clifford, I., Pecchia, M., Mukin, R., Cozzo, C., Ferroukhi, H., & Gorzel, A. (2019). Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs. Annals of Nuclear Energy, 130, 440-451. https://doi.org/10.1016/j.anucene.2019.03.017
Impact of nuclear data uncertainty in the modeling of neutron-induced recoil atom energy distributions in silicon
Griffin, P. J., Koning, A. J., & Rochman, D. (2019). Impact of nuclear data uncertainty in the modeling of neutron-induced recoil atom energy distributions in silicon. IEEE Transactions on Nuclear Science, 66(7), 1719-1729. https://doi.org/10.1109/TNS.2019.2894730
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
Breed-and-burn fuel cycle in molten salt reactors
Hombourger, B., Křepel, J., & Pautz, A. (2019). Breed-and-burn fuel cycle in molten salt reactors. EPJ Nuclear Sciences and Technologies, 5, 15 (10 pp.). https://doi.org/10.1051/epjn/2019026
Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2019). Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique. Presented at the International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Portland, OR, USA: American Nuclear Society.
Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
Hursin, M., Park, J., Kim, W., Siefman, D., Perret, G., Vasiliev, A., … Lee, D. (2019). Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5. Presented at the International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Portland, OR, USA.
TENDL: complete nuclear data library for innovative nuclear science and technology
Koning, A. J., Rochman, D., Sublet, J. C., Dzysiuk, N., Fleming, M., & van der Marck, S. (2019). TENDL: complete nuclear data library for innovative nuclear science and technology. Nuclear Data Sheets, 155, 1-55. https://doi.org/10.1016/j.nds.2019.01.002
 

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