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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
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
The OFFBEAT multi-dimensional fuel behavior solver
Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A. (2020). The OFFBEAT multi-dimensional fuel behavior solver. Nuclear Engineering and Design, 358, 110416 (16 pp.). https://doi.org/10.1016/j.nucengdes.2019.110416
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
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
Detailed modelling of expansion reactivity feedback in fast reactors using OpenFOAM
Fiorina, C., Radman, S., Koc, M. Z., & Pautz, A. (2019). Detailed modelling of expansion reactivity feedback in fast reactors using OpenFOAM. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Illinois: American Nuclear Society (ANS).
Preliminary application of the GeN-Foam multiphysics tool to the analysis of the FFTF sodium fast reactor: coupling thermal-hydraulics and core deformations
Fiorina, C., Radman, S., & Pautz, A. (2019). Preliminary application of the GeN-Foam multiphysics tool to the analysis of the FFTF sodium fast reactor: coupling thermal-hydraulics and core deformations. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2019). La Grange Park: American Nuclear Society (ANS).
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.
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. 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. https://doi.org/10.1051/epjconf/201921103002
 Assessment of nTRACER and parcs performance for VVER configurations
Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2019).  Assessment of nTRACER and parcs performance for VVER configurations. Presented at the International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Portland, USA.
Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
Park, J., Kim, W., Hursin, M., Perret, G., Vasiliev, A., Rochman, D., … Lee, D. (2019). Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5. Annals of Nuclear Energy, 131, 9-22. https://doi.org/10.1016/j.anucene.2019.03.023
A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design
Radman, S., Fiorina, C., Mikityuk, K., & Pautz, A. (2019). A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design. Nuclear Engineering and Design, 355, 110291 (17 pp.). https://doi.org/10.1016/j.nucengdes.2019.110291
Towards the validation of neutron noise simulators: qualification of data acquisition systems
Rais, A., Lamirand, V., Pakari, O., Laureau, A., Pohlus, J., Pohl, C., … Pautz, A. (2019). Towards the validation of neutron noise simulators: qualification of data acquisition systems. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Illinois: American Nuclear Society (ANS).
Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT
Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A. (2019). Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT. In Global/Top Fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS).
Coupling methodology for the multidimensional fuel performance code OFFBEAT and the Monte Carlo neutron transport code Serpent
Scolaro, A., Robert, Y., Fiorina, C., Clifford, I., & Pautz, A. (2019). Coupling methodology for the multidimensional fuel performance code OFFBEAT and the Monte Carlo neutron transport code Serpent. In Global/Top Fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS).
Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
Skorek, T., de Crécy, A., Kovtonyuk, A., Petruzzi, A., Mendizábal, R., de Alfonso, E., … Pautz, A. (2019). Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark. Nuclear Engineering and Design, 354, 110199 (23 pp.). https://doi.org/10.1016/j.nucengdes.2019.110199
 

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