| Validation of standard neutron data libraries for LWR storage pools and transport casks criticality safety evaluations
Kolbe, E., Vasiliev, A., & Zimmermann, M. A. (2008). Validation of standard neutron data libraries for LWR storage pools and transport casks criticality safety evaluations. In ND 2007 - international conference on nuclear data for science and technology 2007 (pp. 799-802). https://doi.org/10.1051/ndata:07441 |
| On the observation of discrepancies in the <sup>16</sup>O(n,<em>α</em>) data between different evaluated nuclear data files
Vasiliev, A., Ferroukhi, H., Zimmermann, M. A., & Kolbe, E. (2008). On the observation of discrepancies in the 16O(n,α) data between different evaluated nuclear data files. In ND 2007 - international conference on nuclear data for science and technology 2007 (pp. 965-968). https://doi.org/10.1051/ndata:07445 |
| Reactor physics studies for assessment of tramp uranium methods
Grimm, P., Vasiliev, A., Wieselquist, W., Ferroukhi, H., & Ledergerber, G. (2012). Reactor physics studies for assessment of tramp uranium methods. In Vol. 2. Advances in reactor physics (pp. 1522-1535). American Nuclear Society. |
| Nuclear data uncertainty propagation in a lattice physics code using stochastic sampling
Wieselquist, W., Vasiliev, A., & Ferroukhi, H. (2012). Nuclear data uncertainty propagation in a lattice physics code using stochastic sampling. In Vol. 4. PHYSOR 2012: advances in reactor physics (pp. 3000-3015). |
| Towards a reference numerical scheme using MCNPX for PWR control rod tip fluence estimations
Ferroukhi, H., Vasiliev, A., Dufresne, A., & Chawla, R. (2012). Towards a reference numerical scheme using MCNPX for PWR control rod tip fluence estimations. In Vol. 1. PHYSOR 2012: advances in reactor physics (pp. 401-417). |
| Stochastic sampling method with MCNPX for nuclear data uncertainty propagation in criticality safety applications
Zhu, T., Vasiliev, A., Wieselquist, W., & Ferroukhi, H. (2012). Stochastic sampling method with MCNPX for nuclear data uncertainty propagation in criticality safety applications. In Vol. 1. PHYSOR 2012: advances in reactor physics (pp. 144-157). |
| Comparison of SERPENT and CASMO-5M for pressurized water reactors models
Hursin, M., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2013). Comparison of SERPENT and CASMO-5M for pressurized water reactors models. In Vol. 3. International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013) (pp. 1565-1576). |
| 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 |
| Validation of two Monte Carlo codes for LWR burnup calculations
Wicaksono, D., Grimm, P., Vasiliev, A., Hursin, M., Perret, G., & Ferroukhi, H. (2014). Validation of two Monte Carlo codes for LWR burnup calculations (p. 1105825 (17 pp.). Presented at the International conference on physics of reactors (PHYSOR 2014). . |
| Validation enhancements of the PSI Fast Neutron Fluence computational scheme using operational PWR experimental data
Dupré, A., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2014). Validation enhancements of the PSI Fast Neutron Fluence computational scheme using operational PWR experimental data. Presented at the American Nuclear Society 2014 student conference. Pennsylvania. |
| Updated validation of the PSI criticality safety evaluation methodology using MCNPX2.7 and ENDF/B-VII.1
Pecchia, M., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2014). Updated validation of the PSI criticality safety evaluation methodology using MCNPX2.7 and ENDF/B-VII.1 (p. 1105709 (15 pp.). Presented at the International conference on physics of reactors (PHYSOR 2014). . |
| Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly
Leray, O., Pecchia, M., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2014). Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly. Presented at the ANS student conference 2014. University Park, PA, USA. |
| 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. |
| 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. |
| 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. |
| 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. |
| Towards application of neutron cross-section uncertainty propagation capability in the criticality safety methodology
Vasiliev, A., Rochman, D., Zhu, T., Pecchia, M., Ferroukhi, H., & Pautz, A. (2015). Towards application of neutron cross-section uncertainty propagation capability in the criticality safety methodology. In ICNC 2015 - international conference on nuclear criticality safety (pp. 606-615). American Nuclear Society. |
| Towards analysis of the bowing effect on burnt nuclear fuel compositions using SERPENT
Li, J., Rochman, D., Herrero, J., Ferrouki, H., Vasiliev, A., & Pautz, A. (2016). Towards analysis of the bowing effect on burnt nuclear fuel compositions using SERPENT (p. (4 pp.). Presented at the American Nuclear Society 2016 student conference. American Nuclear Society. |
| Extention of PSI FNF modeling methodology validation using BWR dosimetry data
Savelli, R., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2016). Extention of PSI FNF modeling methodology validation using BWR dosimetry data (p. (4 pp.). Presented at the American Nuclear Society 2016 student conference. American Nuclear Society. |
| Solution of the BEAVRS benchmark using CASMO-5 / SIMULATE-5 code sequence
Bykov, V., Vasiliev, A., Ferroukhi, H., & Pautz, A. (2016). Solution of the BEAVRS benchmark using CASMO-5 / SIMULATE-5 code sequence. In Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century (pp. 1960-1968). American Nuclear Society. |