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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. In International conference on mathematics computational methods applied to nuclear science and engineering (M&C 2019) (p. (9 pp.). American Nuclear Society (ANS).
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 (p. 03003 (5 pp.). 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 (p. 03002 (5 pp.). https://doi.org/10.1051/epjconf/201921103002
EPR fuel cycle depletion with pin-by-pin code tortin and nodal code SIMULATE5
Mala, P., Pautz, A., & Ferroukhi, H. (2019). EPR fuel cycle depletion with pin-by-pin code tortin and nodal code SIMULATE5. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019) (pp. 1640-1649). American Nuclear Society (ANS).
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. In International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019) (pp. 700-709). American Nuclear Society (ANS).
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) (pp. 2638-2647). 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 (pp. 47-55). 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 (pp. 1174-1183). American Nuclear Society (ANS).
Data assimilation of post irradiation examination experiments to adjust fission yields
Siefman, D., Hursin, M., & Pautz, A. (2019). Data assimilation of post irradiation examination experiments to adjust fission yields. In Z. Ge, N. Shu, Y. Chen, W. Wang, & H. Zhang (Eds.), EPJ web of conferences: Vol. 239. ND 2019: international conference on nuclear data for science and technology (p. 13004 (4 pp.). https://doi.org/10.1051/epjconf/202023913004
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
PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K
Chionis, D., Dokhane, A., Ferroukhi, H., Girardin, G., & Pautz, A. (2018). PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K. In Proceedings of the PHYSOR 2018 (pp. 1001-1012). American Nuclear Society.
PWR neutron noise phenomenology: part II - qualitative comparison against plant data
Chionis, D., Dokhane, A., Ferroukhi, H., Girardin, G., & Pautz, A. (2018). PWR neutron noise phenomenology: part II - qualitative comparison against plant data. In Proceedings of the PHYSOR 2018 (pp. 1013-1024). American Nuclear Society.
A reduced order accelerator for time-dependent segregated neutronic solvers
Fiorina, C., Radman, S., Scolaro, A., & Pautz, A. (2018). A reduced order accelerator for time-dependent segregated neutronic solvers. Annals of Nuclear Energy, 121, 177-185. https://doi.org/10.1016/j.anucene.2018.07.032
On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors
Hombourger, B., Krepel, J., Mikityuk, K., & Pautz, A. (2018). On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 388 (11 pp.). International Atomic Energy Agency.
Representativity analysis of the LWR-PROTEUS Phase II experiments using SHARKX stochastic sampling method
Hursin, M., Siefman, D., Perret, G., & Pautz, A. (2018). Representativity analysis of the LWR-PROTEUS Phase II experiments using SHARKX stochastic sampling method. In ANS international conference on best-estimate plus uncertainties methods (BEPU-2018) (p. 277 (12 pp.). American Nuclear Society.
Testing of a sCVD diamond detection system in the CROCUS reactor
Hursin, M., Weiss, C., Frajtag, P., Lamirand, V., Perret, G., Kavrigin, P., … Griesmayer, E. (2018). Testing of a sCVD diamond detection system in the CROCUS reactor. European Physical Journal A: Hadrons and Nuclei, 54(5), 82 (11 pp.). https://doi.org/10.1140/epja/i2018-12519-1
Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code
Jo, Y., Hursin, M., Lee, D., Ferroukhi, H., & Pautz, A. (2018). Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code. Annals of Nuclear Energy, 111, 141-151. https://doi.org/10.1016/j.anucene.2017.08.061
Design of separated element reflector experiments in CROCUS: PETALE
Lamirand, V., Perret, G., Radman, S., Siefman, D., Frajtag, P., Hursin, M., … Pautz, A. (2018). Design of separated element reflector experiments in CROCUS: PETALE. In M. H. Sparks, K. R. DePriest, & D. W. Vehar (Eds.), Reactor dosimetry: 16th international symposium (pp. 1-14). https://doi.org/10.1520/STP160820170090