| Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis
Nikitin, K., Clifford, I., & Ferroukhi, H. (2024). Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis. Annals of Nuclear Energy, 195, 110147 (12 pp.). https://doi.org/10.1016/j.anucene.2023.110147 |
| Application of CTF subchannel code for BWR reload licensing analysis support
Nikitin, K., Arnold, B., Clifford, I., & Ferroukhi, H. (2023). Application of CTF subchannel code for BWR reload licensing analysis support. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 5569-5578). https://doi.org/10.13182/NURETH20-40978 |
| A decade of research on noble metal chemical addition at PSI – lessons learned
Ritter, S., Grundler, P. V., & Rowthu, S. (2023). A decade of research on noble metal chemical addition at PSI – lessons learned. In International conference on water chemistry in nuclear reactor systems (NPC 2023) (p. (12 pp.). Sfen. |
| Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
Hursin, M., Mala, P., Vasiliev, A., Ferroukhi, H., Liu, Y., Choi, S., & Kochunas, B. (2022). Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices. In International conference on physics of reactors 2022 (PHYSOR 2022) (pp. 2762-2772). American Nuclear Society. |
| Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
Hursin, M., Mala, P., Vasiliev, A., Ferroukhi, H., Liu, Y., Choi, S., & Kochunas, B. (2022). Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices. In Proceedings of the international conference on physics of reactors, PHYSOR 2022. International conference on physics of reactors (pp. 2762-2772). https://doi.org/10.13182/PHYSOR22-37760 |
| CPR estimation by CTF subchannel code with machine learning support
Nikitin, K., Arnold, B., Clifford, I., & Ferroukhi, H. (2022). CPR estimation by CTF subchannel code with machine learning support (p. N13P156 (10 pp.). Presented at the The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13). . |
| Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise
Pázsit, I., Torres, L. A., Hursin, M., Nylén, H., Dykin, V., & Montalvo, C. (2021). Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise. Progress in Nuclear Energy, 138, 103805 (11 pp.). https://doi.org/10.1016/j.pnucene.2021.103805 |
| Reconstructing the axial void velocity profile in BWRS from measurements of the in-core neutron noise
Pázsit, I., Hursin, M., Nylén, H., & Dykin, V. (2021). Reconstructing the axial void velocity profile in BWRS from measurements of the in-core neutron noise. In M. Margulis & P. Blaise (Eds.), EPJ web of conferences: Vol. 247. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future (p. 02013 (8 pp.). https://doi.org/10.1051/epjconf/202124702013 |
| Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
Clifford, I., Pecchia, M., Mukin, R., Cozzo, C., Ferroukhi, H., & Gorzel, A. (2019). Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs. Annals of Nuclear Energy, 130, 440-451. https://doi.org/10.1016/j.anucene.2019.03.017 |
| SCC mitigation in boiling water reactors: platinum deposition and durability on structural materials
Grundler, P. V., Ritter, S., & Veleva, L. (2019). SCC mitigation in boiling water reactors: platinum deposition and durability on structural materials. In J. H. Jackson, D. Paraventi, & M. Wright (Eds.), The minerals, metals & materials series: Vol. 2. Proceedings of the 18th international conference on environmental degradation of materials in nuclear power systems – water reactors (pp. 1685-1700). https://doi.org/10.1007/978-3-030-04639-2_113 |
| BWR-4 ATWS modeling with RELAP5-S3K
Nikitin, K., Mueller, P., Bruder, A., Walser, S., Judd, J., & Hiltbrand, D. (2019). BWR-4 ATWS modeling with RELAP5-S3K. Nuclear Engineering and Design, 344, 38-45. https://doi.org/10.1016/j.nucengdes.2019.01.023 |
| PMSYS: plant management system as a part of Swiss Simulation Platform
Nikitin, K., Clifford, I., & Ferroukhi, H. (2019). PMSYS: plant management system as a part of Swiss Simulation Platform. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18) (pp. 2943-2954). American Nuclear Society (ANS). |
| Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology
Pecchia, M., Ferroukhi, H., Vasiliev, A., & Grimm, P. (2019). Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology. Annals of Nuclear Energy, 129, 67-78. https://doi.org/10.1016/j.anucene.2019.01.047 |
| The use of tapered specimens to evaluate the SCC initiation susceptibility in alloy 182 in BWR and PWR environments
Bai, J., Ritter, S., Seifert, H. P., Vankeerberghen, M., & Bosch, R. W. (2018). The use of tapered specimens to evaluate the SCC initiation susceptibility in alloy 182 in BWR and PWR environments. In J. H. Jackson, D. Paraventi, & M. Wright (Eds.), The minerals, metals & materials series. Proceedings of the 18th international conference on environmental degradation of materials in nuclear power systems – water reactors (pp. 1929-1948). https://doi.org/10.1007/978-3-030-04639-2_131 |
| Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology
Pecchia, M., Ferroukhi, H., Vasiliev, A., & Grimm, P. (2018). Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology. In International Conference on Physics of Reactors, PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems. PHYSOR 2018: reactor physics paving the way towards more efficient systems (p. (12 pp.). Curran Associates, Inc. |
| Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K
Dokhane, A., Ferroukhi, H., & Pautz, A. (2016). Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K. Annals of Nuclear Energy, 96, 344-353. https://doi.org/10.1016/j.anucene.2016.06.016 |
| Impact of containment venting on source term for Fukushima-like BWR scenarios
Rýdl, A., Fernandez-Moguel, L., & Lind, T. (2016). Impact of containment venting on source term for Fukushima-like BWR scenarios (p. N11P1234 (13 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). . |
| Analysis of the OECD/NEA Oskarshamn-2 feedwater transient and stability benchmark with simulate-3K
Dokhane, A., Ferroukhi, H., & Pautz, A. (2014). Analysis of the OECD/NEA Oskarshamn-2 feedwater transient and stability benchmark with simulate-3K. In Proceedings of the international conference on physics of reactors (PHYSOR 2014). PHYSOR 2014 – the role of reactor physics toward a sustainable future (p. 1101708 (14 pp.). |
| Quantification of code, library and cross-section uncertainty effects on the void reactivity coefficient of a BWR UO<sub>2</sub> assembly
Leray, O., Grimm, P., Ferroukhi, H., & Pautz, A. (2014). Quantification of code, library and cross-section uncertainty effects on the void reactivity coefficient of a BWR UO2 assembly (p. 1100815 (14 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 |
