| Post-dryout heat transfer assessment of trace
Aounallah, Y. (2017). Post-dryout heat transfer assessment of trace. In 37th annual conference of the canadian nuclear society and 41st annual cns/cna student conference. Canadian Nuclear Society. |
| Simulations with TRACE of a BWR/4 steam line break under "hot standby" conditions
Aounallah, Y. (2017). Simulations with TRACE of a BWR/4 steam line break under "hot standby" conditions. In Vol. 1. 37th annual conference of the canadian nuclear society & 41st CNS/CNA student conference 2017 (pp. 218-228). Canadian Nuclear Society. |
| TRACE/S3K code coupling simulations of a BWR/4 anticipated transient without scram
Aounallah, Y. (2017). TRACE/S3K code coupling simulations of a BWR/4 anticipated transient without scram. In Vol. 2. Proceedings of the 37th annual conference of the Canadian Nuclear Society & 41st CNS/CNA student conference 2017 (pp. 1000-1013). Canadian Nuclear Society (CNS). |
| SiC cladding behavior: experiments and modelling at PSI
Cozzo, C., Bertsch, J., Fave, L., Rahman, S., Dokhane, A., Krack, M., … Pytel, M. (2017). SiC cladding behavior: experiments and modelling at PSI (p. (10 pp.). Presented at the Water reactor fuel performance meeting 2017 (WRFPM 2017). . |
| Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
Grimm, P., Hursin, M., Perret, G., Siefman, D., & Ferroukhi, H. (2017). Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model. Progress in Nuclear Energy, 101, 280-287. https://doi.org/10.1016/j.pnucene.2017.03.018 |
| Epistemic and aleatory uncertainties in integrated deterministic and probabilistic safety assessment: tradeoff between accuracy and accident simulations
Karanki, D. R., Rahman, S., Dang, V. N., & Zerkak, O. (2017). Epistemic and aleatory uncertainties in integrated deterministic and probabilistic safety assessment: tradeoff between accuracy and accident simulations. Reliability Engineering and System Safety, 162, 91-102. https://doi.org/10.1016/j.ress.2017.01.015 |
| Thermal hydraulic analysis of PWR assembly bowing using subchannel code COBRA-TF
Mukin, R., Clifford, I., Ferroukhi, H., & Seidl, M. (2017). Thermal hydraulic analysis of PWR assembly bowing using subchannel code COBRA-TF (p. (10 pp.). Presented at the 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017). . |
| Kinetic parameter measurements in the Minerve reactor
Perret, G., Geslot, B., Gruel, A., Blaise, P., Di-Salvo, J., De Izarra, G., … Pautz, A. (2017). Kinetic parameter measurements in the Minerve reactor. IEEE Transactions on Nuclear Science, 64(1), 724-734. https://doi.org/10.1109/TNS.2016.2637569 |
| Simulations of level-swell experiments with TRACE
Aounallah, Y. (2016). Simulations of level-swell experiments with TRACE (p. N11A0125 (13 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). . |
| System code validation series based on a consistent plant nodalisation of the ROSA/LSTF integral test facility using TRACE v5.0 Patch 4
Clifford, I., Zerkak, O., Pautz, A., Yao, H., & Freixa, J. (2016). System code validation series based on a consistent plant nodalisation of the ROSA/LSTF integral test facility using TRACE v5.0 Patch 4 (p. N11A0424 (15 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). . |
| 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. |
| Key findings from the artist project on aerosol retention in a dry steam generator
Dehbi, A., Suckow, D., Lind, T., Guentay, S., Danner, S., & Mukin, R. (2016). Key findings from the artist project on aerosol retention in a dry steam generator. Nuclear Engineering and Technology, 48(4), 870-880. https://doi.org/10.1016/j.net.2016.06.001 |
| 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 |
| Bubble reconstruction method for wire-mesh sensors measurements
Mukin, R. V. (2016). Bubble reconstruction method for wire-mesh sensors measurements. Experiments in Fluids, 57(8), 133 (12 pp.). https://doi.org/10.1007/s00348-016-2220-y |
| Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE
Mukin, R., Zerkak, O., & Pautz, A. (2016). Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE (p. N11A0310 (16 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). . |
| Particle deposition modeling in the secondary side of a steam generator bundle model
Mukin, R., & Dehbi, A. (2016). Particle deposition modeling in the secondary side of a steam generator bundle model. Nuclear Engineering and Design, 299, 112-123. https://doi.org/10.1016/j.nucengdes.2015.09.001 |
| Simulation of flow on the secondary side of a steam generator bundle
Mukin, R., & Dehbi, A. (2016). Simulation of flow on the secondary side of a steam generator bundle. In Computational fluid dynamics for nuclear reactor safety-5. (CFD4NRS-5). Workshop proceedings. |
| Influence of URANS turbulence models on in-vessel flow mixing during cold leg accumulator injection
Puragliesi, R., Zerkak, O., & Pautz, A. (2016). Influence of URANS turbulence models on in-vessel flow mixing during cold leg accumulator injection (p. N11P0292 (15 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). . |
| Steady-state CFD simulations of an EPR<sup>TM</sup> reactor pressure vessel: a validation study based on the JULIETTE experiments
Puragliesi, R., Zhou, L., Zerkak, O., & Pautz, A. (2016). Steady-state CFD simulations of an EPRTM reactor pressure vessel: a validation study based on the JULIETTE experiments. Nuclear Engineering and Design, 300, 41-56. https://doi.org/10.1016/j.nucengdes.2015.12.025 |
| New simulation schemes and capabilities for the PHISICS/RELAP5-3D coupled suite
Rabiti, C., Alfonsi, A., & Epiney, A. (2016). New simulation schemes and capabilities for the PHISICS/RELAP5-3D coupled suite. Nuclear Science and Engineering, 182(1), 104-118. https://doi.org/10.13182/NSE14-143 |
