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Scaling analysis of an IBLOCA counterpart test between the ATLAS and LSTF facilities

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Scaling analysis of an IBLOCA counterpart test between the ATLAS and LSTF facilities

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Lorduy, M.; Gallardo Bermell, S.; Verdú Martín, GJ. (2020). Scaling analysis of an IBLOCA counterpart test between the ATLAS and LSTF facilities. Progress in Nuclear Energy. 127:1-13. https://doi.org/10.1016/j.pnucene.2020.103460

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Título: Scaling analysis of an IBLOCA counterpart test between the ATLAS and LSTF facilities
Autor: Lorduy, M. Gallardo Bermell, Sergio Verdú Martín, Gumersindo Jesús
Entidad UPV: Universitat Politècnica de València. Departamento de Ingeniería Química y Nuclear - Departament d'Enginyeria Química i Nuclear
Universitat Politècnica de València. Departamento de Estadística e Investigación Operativa Aplicadas y Calidad - Departament d'Estadística i Investigació Operativa Aplicades i Qualitat
Fecha difusión:
Resumen:
[EN] The experiments carried out in test facilities improve knowledge of the phenomena that would occur in a nuclear power plant during an accident, and support the validation of the thermal-hydraulic codes used in the ...[+]
Palabras clave: Counterpart , IBLOCA , Scaling , ATLAS , LSTF
Derechos de uso: Reserva de todos los derechos
Fuente:
Progress in Nuclear Energy. (issn: 0149-1970 )
DOI: 10.1016/j.pnucene.2020.103460
Editorial:
Elsevier
Versión del editor: https://doi.org/10.1016/j.pnucene.2020.103460
Código del Proyecto:
info:eu-repo/grantAgreement/CSN//STN%2F4524%2F2015%2F640/
Agradecimientos:
The authors are grateful to the Management Board of the OECD-ATLAS Project for their consent to this publication, and thank the Spanish Nuclear Regulatory Body (CSN) for the technical and financial support under the agreement ...[+]
Tipo: Artículo

References

Addabbo, C., & Annunziato, A. (2012). The LOBI Integral System Test Facility Experimental Programme. Science and Technology of Nuclear Installations, 2012, 1-16. doi:10.1155/2012/238019

Bajorek, S. M., Petkov, N., Ohkawa, K., Kemper, R. M., & Ginsberg, A. P. (2001). Realistic Small- and Intermediate-Break Loss-of-Coolant Accident Analysis Using WCOBRA/TRAC. Nuclear Technology, 136(1), 50-62. doi:10.13182/nt01-a3228

Buckingham, E. (1914). On Physically Similar Systems; Illustrations of the Use of Dimensional Equations. Physical Review, 4(4), 345-376. doi:10.1103/physrev.4.345 [+]
Addabbo, C., & Annunziato, A. (2012). The LOBI Integral System Test Facility Experimental Programme. Science and Technology of Nuclear Installations, 2012, 1-16. doi:10.1155/2012/238019

Bajorek, S. M., Petkov, N., Ohkawa, K., Kemper, R. M., & Ginsberg, A. P. (2001). Realistic Small- and Intermediate-Break Loss-of-Coolant Accident Analysis Using WCOBRA/TRAC. Nuclear Technology, 136(1), 50-62. doi:10.13182/nt01-a3228

Buckingham, E. (1914). On Physically Similar Systems; Illustrations of the Use of Dimensional Equations. Physical Review, 4(4), 345-376. doi:10.1103/physrev.4.345

Carlos, S., Querol, A., Gallardo, S., Sanchez-Saez, F., Villanueva, J. F., Martorell, S., & Verdú, G. (2016). Post-test analysis of the ROSA/LSTF and PKL counterpart test. Nuclear Engineering and Design, 297, 81-94. doi:10.1016/j.nucengdes.2015.10.028

Choi, K. Y., Park, H. S., Euh, D. J., Kwon, T. S., & Baek, W. P. (2006). Simulation Capability of the ATLAS Facility for Major Design-Basis Accidents. Nuclear Technology, 156(3), 256-269. doi:10.13182/nt06-a3789

Ishii, M., Revankar, S. T., Leonardi, T., Dowlati, R., Bertodano, M. L., Babelli, I., … Han, J. T. (1998). The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA). Nuclear Engineering and Design, 186(1-2), 177-211. doi:10.1016/s0029-5493(98)00222-2

Lafi, A. Y., & Reyes, J. N. (2000). Comparative Study of Station Blackout Counterpart Tests in APEX and ROSA/AP600. Nuclear Technology, 130(2), 177-183. doi:10.13182/nt00-a3085

Liao, J. (2016). System scaling analysis for modeling small break LOCA using the FULL SPECTRUM LOCA evaluation model. Annals of Nuclear Energy, 87, 443-453. doi:10.1016/j.anucene.2015.09.014

Lorduy-Alós, M., Gallardo, S., & Verdú, G. (2018). Simulation studies on natural circulation phenomena during an SBO accident. Applied Thermal Engineering, 139, 514-523. doi:10.1016/j.applthermaleng.2018.04.130

Muñoz-Cobo, J. L., Berna, C., & Escrivá, A. (2018). Top-down scaling methodology from the LSTF facility to a three loop PWR plant applied to a SBLOCA event – The ROSA 1.2 test. Nuclear Engineering and Design, 327, 248-273. doi:10.1016/j.nucengdes.2017.12.011

Nakamura, H., Watanabe, T., Takeda, T., Maruyama, Y., & Suzuki, M. (2009). OVERVIEW OF RECENT EFFORTS THROUGH ROSA/LSTF EXPERIMENTS. Nuclear Engineering and Technology, 41(6), 753-764. doi:10.5516/net.2009.41.6.753

Takeda, T., & Ohtsu, I. (2017). RELAP5 uncertainty evaluation using ROSA/LSTF test data on PWR 17% cold leg intermediate-break LOCA with single-failure ECCS. Annals of Nuclear Energy, 109, 9-21. doi:10.1016/j.anucene.2017.05.007

TAKEDA, T., MARUYAMA, Y., WATANABE, T., & NAKAMURA, H. (2012). RELAP5 Analyses of OECD/NEA ROSA-2 Project Experiments on Intermediate-Break LOCAs at Hot Leg or Cold Leg. Journal of Power and Energy Systems, 6(2), 87-98. doi:10.1299/jpes.6.87

Wulff, W. (1996). Scaling of thermohydraulic systems. Nuclear Engineering and Design, 163(3), 359-395. doi:10.1016/0029-5493(96)01232-0

Yang, J., Choi, S.-W., Lim, J., Lee, D.-Y., Rassame, S., Hibiki, T., & Ishii, M. (2013). Counterpart experimental study of ISP-42 PANDA tests on PUMA facility. Nuclear Engineering and Design, 258, 249-257. doi:10.1016/j.nucengdes.2013.02.034

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