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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
Validation of axial void profile measured by neutron noise techniques in CROCUS
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Validation of axial void profile measured by neutron noise techniques in CROCUS. In Proceedings of the PHYSOR 2020 (p. 1173 (8 pp.). Cambridge: Nuclear Energy Group.
Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
Khvostov, G. (2020). Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code. Nuclear Engineering and Technology. https://doi.org/10.1016/j.net.2020.05.015
Analytical criteria for fuel fragmentation and burst FGR during a LOCA
Khvostov, G. (2020). Analytical criteria for fuel fragmentation and burst FGR during a LOCA. Nuclear Engineering and Technology. https://doi.org/10.1016/j.net.2020.03.009
Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code
Khvostov, G. (2020). Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code. Nuclear Engineering and Technology, 52(1), 135-147. https://doi.org/10.1016/j.net.2019.07.010
Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
Lamirand, V., Rais, A., Pakari, O., Hursin, M., Laureau, A., Polhus, J., … Pautz, A. (2020). Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX. In Proceedings of the PHYSOR 2020 (p. 1573 (9 pp.). Cambridge: Nuclear Energy Group.
CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
Mylonakis, A. G., Demazière, C., Vinai, P., Lamirand, V., Rais, A., Pakari, O., … Pautz, A. (2020). CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements. In Proceedings of the PHYSOR 2020 (p. 1207 (9 pp.). Cambridge: Nuclear Energy Group.
Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations
Perret, G., Rochman, D., Vasiliev, A., & Ferroukhi, H. (2020). Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations. In Proceedings of the PHYSOR 2020 (p. 1174 (10 pp.). Cambridge: Nuclear Energy Group.
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
A mm<sup>3</sup> fiber-coupled scintillator for in-core thermal neutron detection in CROCUS
Vitullo, F., Lamirand, V., Mosset, J. B., Frajtag, P., Pakari, O., Perret, G., & Pautz, A. (2020). A mm3 fiber-coupled scintillator for in-core thermal neutron detection in CROCUS. IEEE Transactions on Nuclear Science, 67(4), 625-635. https://doi.org/10.1109/TNS.2020.2977530
First tests of a gamma-blind fast neutron detector using a ZnS:Ag-epoxy mixture cast around wavelength-shifting fibers
Wolfertz, A., Adams, R., & Perret, G. (2020). First tests of a gamma-blind fast neutron detector using a ZnS:Ag-epoxy mixture cast around wavelength-shifting fibers. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 971, 164003 (9 pp.). https://doi.org/10.1016/j.nima.2020.164003
First assessments of the dynamic gap conductance model in TRACE
Clifford, I., Cozzo, C., & Ferroukhi, H. (2019). First assessments of the dynamic gap conductance model in TRACE. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18) (pp. 4624-4636). La Grange Park, USA: American Nuclear Society (ANS).
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
Modeling of the U<sub>3</sub>Si<sub>2</sub>/SiC fuel system behavior for a RIA scenario
Cozzo, C., Ngayam-Happy, R., Chen, J. C., Pecchia, M., & Girardin, G. (2019). Modeling of the U3Si2/SiC fuel system behavior for a RIA scenario. In Global/top fuel 2019 (pp. 643-647). LaGrange Park, IL, USA: American Nuclear Society (ANS).
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 (p. (8 pp.). 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 (p. (9 pp.). 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 (p. 03003 (5 pp.). https://doi.org/10.1051/epjconf/201921103003
Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE
Mora, D. F., Mukin, R., Costa Garrido, O., & Niffenegger, M. (2019). Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE. In PVP - American Society of Mechanical Engineers. Pressure vessels and piping division: Vol. 6A. Materials and fabrication: advanced and additive manufacturing and material technologies (pp. PVP2019-94019 (7 pp.). https://doi.org/10.1115/PVP2019-94019
Screening analysis for pressurized thermal shock (PTS) transient scenarios
Mukin, R., Clifford, I., Costa Garrido, O., Mora, D. F., Niffenegger, M., Niceno, B., & Ferroukhi, H. (2019). Screening analysis for pressurized thermal shock (PTS) transient scenarios. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18) (pp. 2536-2549). La Grange Park, USA: American Nuclear Society (ANS).
 

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