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Large scale experiments representing a containment natural circulation loop during an accident scenario
Kapulla, R., Mignot, G., Paranjape, S., Andreani, M., & Paladino, D. (2018). Large scale experiments representing a containment natural circulation loop during an accident scenario. Science and Technology of Nuclear Installations, 2018, 8989070 (12 pp.). https://doi.org/10.1155/2018/8989070
Methods and models for the coupled neutronics and thermal-hydraulics analysis of the CROCUS reactor at EFPL
Rais, A., Siefman, D., Girardin, G., Hursin, M., & Pautz, A. (2015). Methods and models for the coupled neutronics and thermal-hydraulics analysis of the CROCUS reactor at EFPL. Science and Technology of Nuclear Installations, 2015, 237646 (9 pp.). https://doi.org/10.1155/2015/237646
Large scale gas stratification erosion by a vertical helium-air jet
Kapulla, R., Mignot, G., Paranjape, S., Ryan, L., & Paladino, D. (2014). Large scale gas stratification erosion by a vertical helium-air jet. Science and Technology of Nuclear Installations, 2014, 197267 (16 pp.). https://doi.org/10.1155/2014/197267
PSI methodologies for nuclear data uncertainty propagation with CASMO-5M and MCNPX: results for OECD/NEA UAM benchmark phase I
Wieselquist, W., Zhu, T., Vasiliev, A., & Ferroukhi, H. (2013). PSI methodologies for nuclear data uncertainty propagation with CASMO-5M and MCNPX: results for OECD/NEA UAM benchmark phase I. Science and Technology of Nuclear Installations, 2013, 549793 (15 pp.). https://doi.org/10.1155/2013/549793
Remarks on consistent development of plant nodalizations: an example of application to the ROSA integral test facility
Freixa, J., & Manera, A. (2012). Remarks on consistent development of plant nodalizations: an example of application to the ROSA integral test facility. Science and Technology of Nuclear Installations, 2012, 158617 (17 pp.). https://doi.org/10.1155/2012/158617
Large-scale containment cooler performance experiments under accident conditions
Kapulla, R., Mignot, G., & Paladino, D. (2012). Large-scale containment cooler performance experiments under accident conditions. Science and Technology of Nuclear Installations, 2012, 943197 (20 pp.). https://doi.org/10.1155/2012/943197
Analysis of void fraction distribution and departure from nucleate boiling in single subchannel and bundle geometries using subchannel, system, and computational fluid dynamics codes
Kim, T., Petrov, V., Manera, A., & Lo, S. (2012). Analysis of void fraction distribution and departure from nucleate boiling in single subchannel and bundle geometries using subchannel, system, and computational fluid dynamics codes. Science and Technology of Nuclear Installations, 2012, 746467 (20 pp.). https://doi.org/10.1155/2012/746467
PANDA: a multipurpose integral test facility for LWR safety investigations
Paladino, D., & Dreier, J. (2012). PANDA: a multipurpose integral test facility for LWR safety investigations. Science and Technology of Nuclear Installations, 2012, 239319 (9 pp.). https://doi.org/10.1155/2012/239319
Main Results of phase IV BEMUSE project: simulation of LBLOCA in an NPP
Pérez, M., Reventós, F., Batet, L., Pericas, R., Toth, I., Bazin, P., … Del Nevo, A. (2010). Main Results of phase IV BEMUSE project: simulation of LBLOCA in an NPP. Science and Technology of Nuclear Installations, 2010, 219294 (9 pp.). https://doi.org/10.1155/2010/219294
Review of available data for validation of nuresim two-phase CFD software applied to CHF investigations
Bestion, D., Anglart, H., Caraghiaur, D., Péturaud, P., Smith, B., Andreani, M., … Hazi, G. (2009). Review of available data for validation of nuresim two-phase CFD software applied to CHF investigations. Science and Technology of Nuclear Installations, 2009, 214512 (14 pp.). https://doi.org/10.1155/2009/214512
An overview of the pressurized thermal shock issue in the context of the NURESIM project
Lucas, D., Bestion, D., Bodèle, E., Coste, P., Scheuerer, M., D'Auria, F., … Macek, J. (2009). An overview of the pressurized thermal shock issue in the context of the NURESIM project. Science and Technology of Nuclear Installations, 2009, 583259 (13 pp.). https://doi.org/10.1155/2009/583259
Euler-Euler large eddy simulation of a square cross-sectional bubble column using the Neptune_CFD code
Ničeno, B., Boucker, M., & Smith, B. L. (2009). Euler-Euler large eddy simulation of a square cross-sectional bubble column using the Neptune_CFD code. Science and Technology of Nuclear Installations, 2009, 410272 (8 pp.). https://doi.org/10.1155/2009/410272
Gas cooled fast reactor research and development in the European Union
Stainsby, R., Peers, K., Mitchell, C., Poette, C., Mikityuk, K., & Somers, J. (2009). Gas cooled fast reactor research and development in the European Union. Science and Technology of Nuclear Installations, 2009, 238624 (7 pp.). https://doi.org/10.1155/2009/238624
International standard problems and small break loss-of-coolant accident (SBLOCA)
Aksan, N. (2008). International standard problems and small break loss-of-coolant accident (SBLOCA). Science and Technology of Nuclear Installations, 2008, 814572 (22 pp.). https://doi.org/10.1155/2008/814572
Natural circulation characteristics at low-pressure conditions through PANDA experiments and ATHLET simulations
Paladino, D., Huggenberger, M., & Schäfer, F. (2008). Natural circulation characteristics at low-pressure conditions through PANDA experiments and ATHLET simulations. Science and Technology of Nuclear Installations, 2008, 874969 (14 pp.). https://doi.org/10.1155/2008/874969