| Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone
Dokhane, A., Judd, J., Gajev, I., Zerkak, O., Ferroukhi, H., & Kozlowski, T. (2017). Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone. Annals of Nuclear Energy, 102, 190-199. https://doi.org/10.1016/j.anucene.2016.12.015 |
| Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
Hursin, M., Bogetic, S., Dohkane, A., Canepa, S., Zerkak, O., Ferroukhi, H., & Pautz, A. (2017). Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19. Annals of Nuclear Energy, 101, 559-575. https://doi.org/10.1016/j.anucene.2016.11.001 |
| Testing the NURESIM platform on a PWR main steam line break benchmark
Kliem, S., Kozmenkov, Y., Hadek, J., Perin, Y., Fouquet, F., Bernard, F., … Mala, P. (2017). Testing the NURESIM platform on a PWR main steam line break benchmark. Nuclear Engineering and Design, 321, 8-25. https://doi.org/10.1016/j.nucengdes.2017.05.028 |
| Modeling of axial distribution of released fission gas in KKL BWR fuel rods during base irradiation
Brankov, V., Khvostov, G., Mikityuk, K., Pautz, A., Restani, R., Abolhassani, S., … Wiesenack, W. (2015). Modeling of axial distribution of released fission gas in KKL BWR fuel rods during base irradiation. In TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1 (pp. 609-619). European Nuclear Society. |
| Enhancement and Validation of BWR MCNP Activation Simulations for Swiss Decommissioning Planning
Bykov, V., Volmert, B., & Pautz, A. (2015). Enhancement and Validation of BWR MCNP Activation Simulations for Swiss Decommissioning Planning. Presented at the 2015 American Nuclear Society Student Conference. College Station, TX, USA. |
| Scalability benchmarking methodology for hybrid parallel core calculations with the code nTRACER
Canepa, S., Krack, M., Ferroukhi, H., & Pautz, A. (2015). Scalability benchmarking methodology for hybrid parallel core calculations with the code nTRACER. In Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015) (pp. 2819-2831). American Nuclear Society. |
| Computational fluid dynamics analysis of the fluid flow and heat transfer in the core bypass region of a PWR
Clifford, I., Vasiliev, A., Zerkak, O., Ferroukhi, H., & Pautz, A. (2015). Computational fluid dynamics analysis of the fluid flow and heat transfer in the core bypass region of a PWR. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 7806-7819). American Nuclear Society. |
| Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data
Dupré, A., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2015). Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data. Annals of Nuclear Energy, 85, 820-829. https://doi.org/10.1016/j.anucene.2015.06.040 |
| GeN-Foam: a novel multi-physics solver for reactor analysis - status and ongoing developments
Fiorina, C., Mikityuk, K., & Pautz, A. (2015). GeN-Foam: a novel multi-physics solver for reactor analysis - status and ongoing developments. In G. Federici, M. L. Corradini, A. C. Klein, N. A. Uckan, G. Rimpault, D. G. Cacuci, … S. H. Chang (Eds.), Transactions of the American Nuclear Society: Vol. 113. Proceedings of the American Nuclear Society (pp. 1132-1134). |
| Fuel cycle analysis of a Molten Salt Reactor for Breed-and-Burn mode
Hombourger, B., Pautz, A., Krepel, J., & Mikityuk, K. (2015). Fuel cycle analysis of a Molten Salt Reactor for Breed-and-Burn mode. In Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015) (pp. 910-916). SFEN. |
| Parametric lattice study of a graphite-moderated molten salt reactor
Hombourger, B. A., Křepel, J., Mikityuk, K., & Pautz, A. (2015). Parametric lattice study of a graphite-moderated molten salt reactor. Journal of Nuclear Engineering and Radiation Science, 1(1), 011009 (8 pp.). https://doi.org/10.1115/1.4026401 |
| BWR full core analysis with SERPENT/SIMULATE-3 hybrid stochastic/determinstic code sequence
Hursin, M., Rossinelli, L., Ferroukhi, H., & Pautz, A. (2015). BWR full core analysis with SERPENT/SIMULATE-3 hybrid stochastic/determinstic code sequence. In Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015) (pp. 1794-1806). American Nuclear Society. |
| Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis
Hursin, M., Perret, G., & Pautz, A. (2015). Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis. Annals of Nuclear Energy, 77, 300-309. https://doi.org/10.1016/j.anucene.2014.11.019 |
| Development, verification and test application of a hybrid CASMO-5/SERPENT depletion scheme
Leray, O., Pecchia, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Perrier, H. (2015). Development, verification and test application of a hybrid CASMO-5/SERPENT depletion scheme. In Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015) (pp. 1781-1793). American Nuclear Society. |
| Preparation of pin-by-pin nuclear libraries with superhomogenization method for nTRACER and DORT core calculations
Mala, P., Canepa, S., Ferroukhi, H., & Pautz, A. (2015). Preparation of pin-by-pin nuclear libraries with superhomogenization method for nTRACER and DORT core calculations. In Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015) (pp. 775-786). American Nuclear Society. |
| Effects of stoichiometry on the defect clustering in uranium dioxide
Ngayam-Happy, R., Krack, M., & Pautz, A. (2015). Effects of stoichiometry on the defect clustering in uranium dioxide. Journal of Physics: Condensed Matter, 27(45), 455401 (13 pp.). https://doi.org/10.1088/0953-8984/27/45/455401 |
| Advanced calculation methodology for manufacturing and technological parameters' uncertainties propagation at arbitrary level of lattice elements grouping
Pecchia, M., Vasiliev, A., Leray, O., Ferroukhi, H., & Pautz, A. (2015). Advanced calculation methodology for manufacturing and technological parameters' uncertainties propagation at arbitrary level of lattice elements grouping. Journal of Nuclear Science and Technology, 52(7-8), 1084-1092. https://doi.org/10.1080/00223131.2015.1032382 |
| COMPLINK: a versatile tool for automatizing the representation of material data in MCNP models
Pecchia, M., Herrero, J. J., Ferroukhi, H., Vasiliev, A., Canepa, S., & Pautz, A. (2015). COMPLINK: a versatile tool for automatizing the representation of material data in MCNP models. In ICNC 2015 - international conference on nuclear criticality safety (pp. 513-522). American Nuclear Society. |
| Criticality safety evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology
Pecchia, M., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2015). Criticality safety evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology. Annals of Nuclear Energy, 83, 226-235. https://doi.org/10.1016/j.anucene.2015.03.052 |
| Sodium void map preparation for the safety analysis of Sodium-cooled Fast Reactors by using the Monte Carlo code Serpent
Pelloni, S., Aufiero, M., Bortot, S., Krepel, J., Mikityuk, K., Panadero, A. L., … Sciora, P. (2015). Sodium void map preparation for the safety analysis of Sodium-cooled Fast Reactors by using the Monte Carlo code Serpent. In Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). |
