| Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark
Vasiliev, A., Canepa, S., Ferroukhi, H., Boyarinov, V. F., Fomichenko, P. A., Joo, H. G., & Ryu, M. (2019). Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark. Annals of Nuclear Energy, 134, 235-243. https://doi.org/10.1016/j.anucene.2019.06.002 |
| 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 |
| Nodal and pin-by-pin calculations comparison with codes SIMULATE-5 and DYN3D
Mala, P., Pautz, A., Canepa, S., & Ferroukhi, H. (2017). Nodal and pin-by-pin calculations comparison with codes SIMULATE-5 and DYN3D. In International conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017) (p. (9 pp.). Korean Nuclear Society. |
| Comparative study of CASMO-5/simulate-5 and nTRACER for EPR core analyses
Canepa, S., Ferroukhi, H., Min, R., & Joo, H. G. (2016). Comparative study of CASMO-5/simulate-5 and nTRACER for EPR core analyses. In Vol. 2. International congress on advances in nuclear power plants, ICAPP 2016 (pp. 1436-1445). American Nuclear Society. |
| Full core LOCA analysis for BWR/6 - methodology and first results
Cozzo, C., Epiney, A., Canepa, S., Ferroukhi, H., Zerkak, O., Khvostov, G., … Gorzel, A. (2016). Full core LOCA analysis for BWR/6 - methodology and first results. In Top Fuel 2016. LWR fuels with enhanced safety and performance (pp. 1135-1144). American Nuclear Society. |
| Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors
Epiney, A., Canepa, S., Zerkak, O., & Ferroukhi, H. (2016). Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors. Nuclear Technology, 196(2), 223-237. https://doi.org/10.13182/NT16-47 |
| 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. |
| Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event
Epiney, A., Canepa, S., Zerkak, O., & Ferroukhi, H. (2015). Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 2157-2170). American Nuclear Society. |
| Computational scheme for burnup credit applied to long term waste disposal
Herrero, J. J., Pecchia, M., Ferroukhi, H., Canepa, S., Vasiliev, A., & Caruso, S. (2015). Computational scheme for burnup credit applied to long term waste disposal. In ICNC 2015 - international conference on nuclear criticality safety (pp. 1783-1791). 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. |
| 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. |
| Effects of advanced radial submeshing methods on pin power reconstruction for an EPR core design
Mala, P., Canepa, S., Ferroukhi, H., & Pautz, A. (2014). Effects of advanced radial submeshing methods on pin power reconstruction for an EPR core design (p. 1105669 (12 pp.). Presented at the International conference on physics of reactors (PHYSOR 2014). . |
| Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs
Vasiliev, A., Wieselquist, W., Ferroukhi, H., Canepa, S., Heldt, J., & Ledergerber, G. (2014). Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs. Progress in nuclear science and technology: Vol. 4. (pp. 99-103). Presented at the 12th international conference on radiation shielding. https://doi.org/10.15669/pnst.4.99 |
| Convergence studies of deterministic methods for LWR explicit reflector methodology
Canepa, S., Hursin, M., Ferroukhi, H., & Pautz, A. (2013). Convergence studies of deterministic methods for LWR explicit reflector methodology. In Vol. 4. International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013) (pp. 2868-2876). |
| Preparation of nuclear libraries with deterministic and stochastic methods for LWR reflectors
Canepa, S., Hursin, M., Ferroukhi, H., & Pautz, A. (2013). Preparation of nuclear libraries with deterministic and stochastic methods for LWR reflectors. In Vol. 4. International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013) (pp. 2924-2934). |
| Transition to CASMO-5M and SIMULATE-3K for stability analyses of the Swiss boiling water reactors
Dokhane, A., Canepa, S., & Ferroukhi, H. (2013). Transition to CASMO-5M and SIMULATE-3K for stability analyses of the Swiss boiling water reactors. Nuclear Technology, 183(3), 341-353. https://doi.org/10.13182/NT13-A19423 |
| Post-analysis of a turbine trip test at a BWR/6 using the TRACE/S3K coupled code
Nikitin, K., Gudmundsson, T., Canepa, S., Zerkak, O., Ferroukhi, H., & Pautz, A. (2013). Post-analysis of a turbine trip test at a BWR/6 using the TRACE/S3K coupled code (pp. NURETH15-431 (12 pp.). Presented at the 15th international topical meeting on nuclear reactor thermal-hydraulics, NURETH-15. . |
