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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.