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A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity
Baccou, J., Glantz, T., Ghione, A., Sargentini, L., Fillion, P., Damblin, G., … Adorni, M. (2024). A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity. Nuclear Engineering and Design, 421, 113035 (16 pp.). https://doi.org/10.1016/j.nucengdes.2024.113035
Core melt down and vessel failure: a coupled problem
Duijvestijn, G., & Birchley, J. (1999). Core melt down and vessel failure: a coupled problem. Nuclear Engineering and Design, 191(1), 17-30. https://doi.org/10.1016/S0029-5493(99)00050-3
Benchmark exercise on ELSMOR passive heat removal system
Bersano, A., Lombardo, C., Alblouwy, F., Karppinen, I., Silde, A., Nikitin, K., … Weyermann, F. (2024). Benchmark exercise on ELSMOR passive heat removal system. Nuclear Engineering and Design, 419, 112961 (14 pp.). https://doi.org/10.1016/j.nucengdes.2024.112961
Stress corrosion cracking of low-alloy, reactor-pressure-vessel steels in oxygenated, high-temperature water
Heldt, J., & Seifert, H. P. (2001). Stress corrosion cracking of low-alloy, reactor-pressure-vessel steels in oxygenated, high-temperature water. Nuclear Engineering and Design, 206(1), 57-89. https://doi.org/10.1016/S0029-5493(00)00381-2
Cooling elements for passive heat removal
Warnke, E. P., Kanzleiter, T. F., Hicken, E. F., & Dreier, J. (2001). Cooling elements for passive heat removal. Nuclear Engineering and Design, 207(1), 33-40. https://doi.org/10.1016/S0029-5493(00)00423-4
Experimental results of thermocline evolution in a water pool under combined effect of steam venting and water injection
Paranjape, S., Kapulla, R., Kudinov, P., Chae, M. S., & Paladino, D. (2024). Experimental results of thermocline evolution in a water pool under combined effect of steam venting and water injection. Nuclear Engineering and Design, 419, 112914 (17 pp.). https://doi.org/10.1016/j.nucengdes.2024.112914
TEPSS - Technology enhancement for passive safety systems
Hart, J., Slegers, W. J. M., de Boer, S. L., Huggenberger, M., Lopez Jimenez, J., Munoz-Cobo Gonzalez, J. L., & Reventos Puigjaner, F. (2001). TEPSS - Technology enhancement for passive safety systems. Nuclear Engineering and Design, 209(1-3), 243-252. https://doi.org/10.1016/S0029-5493(01)00407-1
On the prediction of the reactor vessel integrity under severe accident loadings (RPVSA)
Krieg, R., Devos, J., Caroli, C., Solomos, G., Ennis, P. J., & Kalkhof, D. (2001). On the prediction of the reactor vessel integrity under severe accident loadings (RPVSA). Nuclear Engineering and Design, 209(1-3), 117-125. https://doi.org/10.1016/S0029-5493(01)00394-6
Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA)
Friesen, E., Meseth, J., Guentay, S., Suckow, D., López Jiménez, J., Herranz, L., … Mazzocchi, L. (2001). Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA). Nuclear Engineering and Design, 209(1-3), 253-262. https://doi.org/10.1016/S0029-5493(01)00408-3
On the boundary conditions of the <em>k-ε</em> model in 3D coarse-mesh models for containment analysis
Analytis, G. T., & Andreani, M. (2001). On the boundary conditions of the k-ε model in 3D coarse-mesh models for containment analysis. Nuclear Engineering and Design, 205(1-2), 53-67. https://doi.org/10.1016/S0029-5493(00)00373-3
Influence of the distribution of noncondensibles on passive containment condenser performance in PANDA
Bandurski, T., Huggenberger, M., Dreier, J., Aubert, C., Putz, F., Gamble, R. E., & Yadigaroglu, G. (2001). Influence of the distribution of noncondensibles on passive containment condenser performance in PANDA. Nuclear Engineering and Design, 204(1-3), 285-298. https://doi.org/10.1016/S0029-5493(00)00317-4
Implementation and assessment of the renormalization group (RNG), quadratic and cubic non-linear eddy viscosity <em>k-ε </em>models in GOTHIC
Analytis, G. T. (2001). Implementation and assessment of the renormalization group (RNG), quadratic and cubic non-linear eddy viscosity k-ε models in GOTHIC. Nuclear Engineering and Design, 210(1-3), 177-191. https://doi.org/10.1016/S0029-5493(01)00417-4
High-resolution experiments for mixing in large enclosures
Mao, J., Manera, A., & Petrov, V. (2024). High-resolution experiments for mixing in large enclosures. Nuclear Engineering and Design, 417, 112828 (11 pp.). https://doi.org/10.1016/j.nucengdes.2023.112828
An NEA/OECD benchmark-experiment for the validation of CFD for mixing and thermal fatigue in T-junction dead leg flows
Kristian, A., Richard, H., Pascal, V., Braillard, O., Manera, A., & Petrov, V. (2024). An NEA/OECD benchmark-experiment for the validation of CFD for mixing and thermal fatigue in T-junction dead leg flows. Nuclear Engineering and Design, 417, 112813 (16 pp.). https://doi.org/10.1016/j.nucengdes.2023.112813
The influence of droplet breakup model on the prediction of reactor core parameters during reflood conditions
Al-Yahia, O. S., Bernard, M., Clifford, I., Perret, G., Bajorek, S., & Ferroukhi, H. (2024). The influence of droplet breakup model on the prediction of reactor core parameters during reflood conditions. Nuclear Engineering and Design, 416, 112815 (16 pp.). https://doi.org/10.1016/j.nucengdes.2023.112815
MELCOR/MACCS simulation of the TMI-2 severe accident and initial recovery phases, off-site fission product release and consequences
Haste, T., Birchley, J., Cazzoli, E., & Vitazkova, J. (2006). MELCOR/MACCS simulation of the TMI-2 severe accident and initial recovery phases, off-site fission product release and consequences. Nuclear Engineering and Design, 236(10), 1099-1112. https://doi.org/10.1016/j.nucengdes.2005.11.012
CFD analyses of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres
Dehbi, A., & Kapulla, R. (2023). CFD analyses of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres. Nuclear Engineering and Design, 415, 112710 (12 pp.). https://doi.org/10.1016/j.nucengdes.2023.112710
An analytical comparative exercise on the OECD-SETH PKL E2.2 experiment
Reventós, F., Freixa, J., Batet, L., Pretel, C., Luebbesmeyer, D., Spaziani, D., … Wegner, R. (2008). An analytical comparative exercise on the OECD-SETH PKL E2.2 experiment. Nuclear Engineering and Design, 238(4), 1146-1154. https://doi.org/10.1016/j.nucengdes.2007.10.002
CFD simulation of the Vattenfall 1/5th-scale PWR model for boron dilution studies
Dury, T. V., Hemström, B., & Shepel, S. V. (2008). CFD simulation of the Vattenfall 1/5th-scale PWR model for boron dilution studies. Nuclear Engineering and Design, 238(3), 577-589. https://doi.org/10.1016/j.nucengdes.2007.02.038
A numerical investigation of three-dimensional flows in large volumes in the context of passive containment cooling in BWRs
Smith, B. L. (2007). A numerical investigation of three-dimensional flows in large volumes in the context of passive containment cooling in BWRs. Nuclear Engineering and Design, 237(11), 1175-1184. https://doi.org/10.1016/j.nucengdes.2007.02.001
 

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