- -

Analysis of the Core Exit Temperature and the Peak Cladding Temperature during a SBLOCA. Application to a scaled-up model

RiuNet: Repositorio Institucional de la Universidad Politécnica de Valencia

Compartir/Enviar a

Citas

Estadísticas

  • Estadisticas de Uso

Analysis of the Core Exit Temperature and the Peak Cladding Temperature during a SBLOCA. Application to a scaled-up model

Mostrar el registro completo del ítem

Querol, A.; Gallardo Bermell, S.; Verdú Martín, GJ. (2016). Analysis of the Core Exit Temperature and the Peak Cladding Temperature during a SBLOCA. Application to a scaled-up model. Journal of Nuclear Engineering and Radiation Science. 2(2):1-6. https://doi.org/10.1115/1.4031016

Por favor, use este identificador para citar o enlazar este ítem: http://hdl.handle.net/10251/98929

Ficheros en el ítem

Metadatos del ítem

Título: Analysis of the Core Exit Temperature and the Peak Cladding Temperature during a SBLOCA. Application to a scaled-up model
Autor: Querol, A. 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
Fecha difusión:
Resumen:
[EN] During Loss-Of-Coolant Accidents (LOCA), operators may start Accident Management (AM) actions when the Core Exit Temperature (CET) measured by thermocouples exceeds a certain value. However, a significant time delay ...[+]
Palabras clave: Core Exit Temperature , Peak Cladding Temperature , SBLOCA , Scaled-up model.
Derechos de uso: Cerrado
Fuente:
Journal of Nuclear Engineering and Radiation Science. (issn: 2332-8983 )
DOI: 10.1115/1.4031016
Editorial:
ASME International
Versión del editor: http://doi.org/10.1115/1.4031016
Código del Proyecto:
info:eu-repo/grantAgreement/MECD//AP2009-2600/ES/AP2009-2600/
info:eu-repo/grantAgreement/MICINN//ENE2011-22823/ES/VALIUN-3D: VERIFICACION, VALIDACION, MEJORA Y CUANTIFICACION DE INCERTIDUMBRE EN CODIGOS 3D-NTH PARA ANALISIS DE SEGURIDAD/
info:eu-repo/grantAgreement/MINECO//ENE2012-34585/ES/Desarrollo de una plataforma multifísica de altas prestaciones para simulaciones Termohidráulico-Neutrónicas en ingeniería nuclear/
info:eu-repo/grantAgreement/GVA//PROMETEOII%2F2014%2F008/ES/New improved capacities in 3d-VALKIN (Valencian Neutronic Kinetisc). N3D-VALKIN/
info:eu-repo/grantAgreement/GVA//ACOMP%2F2013%2F237/
Agradecimientos:
The authors are grateful to the Management Board of the OECD-NEA ROSA Project; thus, this work contains findings produced within this project. This work is partially supported by the Grant-in-Aid for Scientific Research ...[+]
Tipo: Artículo

References

Tóth, I., Prior, R., Sandervag, O., Umminger, K., Nakamura, H., Muellner, N., Cherubini, M., Del Nevo, A., D’Auria, F., Dreier, J., Alonso, J. R., and Amri, A., 2010, “Core Exit Temperature (CET) Effectiveness in Accident Management of Nuclear Power Reactors,” Committee on the Safety of Nuclear Installations, OECD, Nuclear Energy Agency, Tech. Rep. NEA/CSNI/R(2010)9.

Freixa, J., Martínez-Quiroga, V., Zerkak, O., & Reventós, F. (2015). Modelling guidelines for core exit temperature simulations with system codes. Nuclear Engineering and Design, 286, 116-129. doi:10.1016/j.nucengdes.2015.02.003

Adams, J. P., and McCreery, G. E., 1983, “Detection of Inadequate Core Cooling With Core Exit Thermocouples: LOFT PWR Experience,” U.S. Nuclear Regulatory Commission, Washington, NUREG/CR-3386. [+]
Tóth, I., Prior, R., Sandervag, O., Umminger, K., Nakamura, H., Muellner, N., Cherubini, M., Del Nevo, A., D’Auria, F., Dreier, J., Alonso, J. R., and Amri, A., 2010, “Core Exit Temperature (CET) Effectiveness in Accident Management of Nuclear Power Reactors,” Committee on the Safety of Nuclear Installations, OECD, Nuclear Energy Agency, Tech. Rep. NEA/CSNI/R(2010)9.

Freixa, J., Martínez-Quiroga, V., Zerkak, O., & Reventós, F. (2015). Modelling guidelines for core exit temperature simulations with system codes. Nuclear Engineering and Design, 286, 116-129. doi:10.1016/j.nucengdes.2015.02.003

Adams, J. P., and McCreery, G. E., 1983, “Detection of Inadequate Core Cooling With Core Exit Thermocouples: LOFT PWR Experience,” U.S. Nuclear Regulatory Commission, Washington, NUREG/CR-3386.

Suzuki, M., 1993, “Characteristic Responses of Core Exit Thermocouples During Inadequate Core Cooling in Small Break LOCA Experiments Conducted at LSTF of ROSA-IV Program,” Proceedings of ICONE2, San Francisco, CA, American Society of Mechanical Engineers, United Engineering Center, New York, Vol. 1, pp. 63–68.

SUZUKI, M., & NAKAMURA, H. (2010). Reliability of Core Exit Thermocouple for Accident Management Action during SBLOCA and Abnormal Transient Tests at ROSA/LSTF. Journal of Nuclear Science and Technology, 47(12), 1193-1205. doi:10.1080/18811248.2010.9720986

Thermalhydraulic Safety Research Group, Nuclear Safety Research Center, 2006, “Final Data Report of OECD/NEA ROSA Project Test 6-1 (1.9% Pressure Vessel Upper-Head Small Break LOCA Experiment SB-PV-09 in JAEA),” Japan Atomic Energy Agency, Tokai-mura, Japan.

The ROSA-V Group, 2003, “ROSA-V Large Scale Test Facility (LSTF) System Description for the Third and Fourth Simulated Fuel Assemblies,” JAERI-Tech, Tokai-mura.

Gallardo, S., Abella, V., and Verdú, G., 2010, “Assessment of TRACE 5.0 Against ROSA Test 6-1, Vessel Upper Head SBLOCA,” U.S. Nuclear Regulatory Commission, Washington, NUREG/IA-0245.

Freixa, J., & Manera, A. (2010). Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE. Nuclear Engineering and Design, 240(7), 1779-1788. doi:10.1016/j.nucengdes.2010.02.007

Freixa, J., & Manera, A. (2011). Verification of a TRACE EPR™ model on the basis of a scaling calculation of an SBLOCA ROSA test. Nuclear Engineering and Design, 241(3), 888-896. doi:10.1016/j.nucengdes.2010.12.016

Queral, C., González-Cadelo, J., Jimenez, G., & Villalba, E. (2011). Accident Management Actions in an Upper-Head Small-Break Loss-of-Coolant Accident with High-Pressure Safety Injection Failed. Nuclear Technology, 175(3), 572-593. doi:10.13182/nt11-a12507

Queral, C., González-Cadelo, J., Jimenez, G., Villalba, E., and Perez, J., 2013, “Simulation of LSTF Upper Head Break (OECD/NEA ROSA Test 6.1) With TRACE Code. Application to a PWR NPP Model,” U.S. Nuclear Regulatory Commission, Washington, NUREG/IA-0426.

Querol, A., Gallardo, S., & Verdú, G. (2015). Simulation of a SBLOCA in a hot leg. Scaling considerations and application to a nuclear power plant. Nuclear Engineering and Design, 283, 81-99. doi:10.1016/j.nucengdes.2014.10.006

Liu, T.-J., Lee, C.-H., & Way, Y.-S. (1997). IIST and LSTF counterpart test on PWR station blackout transient. Nuclear Engineering and Design, 167(3), 357-373. doi:10.1016/s0029-5493(96)01302-7

D’Auria, F., & Galassi, G. M. (2010). Scaling in nuclear reactor system thermal-hydraulics. Nuclear Engineering and Design, 240(10), 3267-3293. doi:10.1016/j.nucengdes.2010.06.010

Petelin, S., Mavko, B., Končar, B., & Hassan, Y. A. (2007). Scaling of the Small-Scale Thermal-Hydraulic Transient to the Real Nuclear Power Plant. Nuclear Technology, 158(1), 56-68. doi:10.13182/nt07-a3824

[-]

recommendations

 

Este ítem aparece en la(s) siguiente(s) colección(ones)

Mostrar el registro completo del ítem