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FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits
Khvostov, G., & Gorzel, A. (2021). FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits. Nuclear Engineering and Technology, 53(11), 3741-3758. https://doi.org/10.1016/j.net.2021.06.001
Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2021). Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling. Journal of Nuclear Materials, 555, 153138 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153138
Investigation on the effect of eccentricity for fuel disc irradiation tests
Scolaro, A., Van Uffelen, P., Fiorina, C., Schubert, A., Clifford, I., & Pautz, A. (2021). Investigation on the effect of eccentricity for fuel disc irradiation tests. Nuclear Engineering and Technology, 53(5), 1602-1611. https://doi.org/10.1016/j.net.2020.11.003
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, 206(10), 1566-1583. 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.). 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, 52(12), 2887-2900. 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, 52(10), 2402-2409. 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
Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage
Konarski, P., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2020). Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage. Kerntechnik, 85(6), 419-425. https://doi.org/10.3139/124.200072
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.). Nuclear Energy Group.
Crack propagation modeling in a PWR under PTS Using XFEM
Mora, D. F., Niffenegger, M., & Mukin, R. (2020). Crack propagation modeling in a PWR under PTS Using XFEM. In Pressure vessels and piping conference: Vol. 6. Volume 6: materials and fabrication (p. V006T06A001). https://doi.org/10.1115/PVP2020-21026
Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
Mora, D. F., Costa Garrido, O., Mukin, R., & Niffenegger, M. (2020). Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach. Engineering Fracture Mechanics, 238, 107258 (16 pp.). https://doi.org/10.1016/j.engfracmech.2020.107258
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.). 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.). 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
Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations
Vasiliev, A., Pecchia, M., Rochman, D., Perret, G., Ferroukhi, H., Laureau, A., … Pautz, A. (2020). Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations. 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. 22001 (6 pp.). https://doi.org/10.1051/epjconf/202023922001
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). American Nuclear Society (ANS).
 

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