During loss-of-coolant accidents (LOCAs), 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 and temperature discrepancy in the superheat detection were observed in several facilities. This work is focused on clarifying CET thermocouple responses versus peak cladding temperature (PCT) and studying if the same physical phenomena are reproduced in two TRACE5 models with different geometry (a large-scale test facility (LSTF) and a scaled-up LSTF) during a pressure vessel (PV) upper head small break LOCA (SBLOCA). Results obtained show that the delay between the core uncover and the CET excursion is reproduced in both cases.
Skip Nav Destination
Article navigation
April 2016
Research-Article
Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model
Andrea Querol,
Andrea Querol
1
Instituto de Seguridad Industrial,
Radiofísica y Medioambiental (ISIRYM),
e-mail: anquevi@upv.es
Radiofísica y Medioambiental (ISIRYM),
Universitat Politècnica de València
, Camino de Vera s/n, Valencia 46022
, Spain
e-mail: anquevi@upv.es
1Corresponding author.
Search for other works by this author on:
Sergio Gallardo,
Sergio Gallardo
Instituto de Seguridad Industrial,
Radiofísica y Medioambiental (ISIRYM),
e-mail: sergalbe@iqn.upv.es
Radiofísica y Medioambiental (ISIRYM),
Universitat Politècnica de València
, Camino de Vera s/n, Valencia 46022
, Spain
e-mail: sergalbe@iqn.upv.es
Search for other works by this author on:
Gumersindo Verdú
Gumersindo Verdú
Instituto de Seguridad Industrial,
Radiofísica y Medioambiental (ISIRYM),
e-mail: gverdu@iqn.upv.es
Radiofísica y Medioambiental (ISIRYM),
Universitat Politècnica de València
, Camino de Vera s/n, Valencia 46022
, Spain
e-mail: gverdu@iqn.upv.es
Search for other works by this author on:
Andrea Querol
Instituto de Seguridad Industrial,
Radiofísica y Medioambiental (ISIRYM),
e-mail: anquevi@upv.es
Radiofísica y Medioambiental (ISIRYM),
Universitat Politècnica de València
, Camino de Vera s/n, Valencia 46022
, Spain
e-mail: anquevi@upv.es
Sergio Gallardo
Instituto de Seguridad Industrial,
Radiofísica y Medioambiental (ISIRYM),
e-mail: sergalbe@iqn.upv.es
Radiofísica y Medioambiental (ISIRYM),
Universitat Politècnica de València
, Camino de Vera s/n, Valencia 46022
, Spain
e-mail: sergalbe@iqn.upv.es
Gumersindo Verdú
Instituto de Seguridad Industrial,
Radiofísica y Medioambiental (ISIRYM),
e-mail: gverdu@iqn.upv.es
Radiofísica y Medioambiental (ISIRYM),
Universitat Politècnica de València
, Camino de Vera s/n, Valencia 46022
, Spain
e-mail: gverdu@iqn.upv.es
1Corresponding author.
Manuscript received March 16, 2015; final manuscript received June 26, 2015; published online February 29, 2016. Assoc. Editor: Leon Cizelj.
ASME J of Nuclear Rad Sci. Apr 2016, 2(2): 021020 (6 pages)
Published Online: February 29, 2016
Article history
Received:
March 16, 2015
Revision Received:
June 26, 2015
Accepted:
July 13, 2015
Citation
Querol, A., Gallardo, S., and Verdú, G. (February 29, 2016). "Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model." ASME. ASME J of Nuclear Rad Sci. April 2016; 2(2): 021020. https://doi.org/10.1115/1.4031016
Download citation file:
41
Views
Get Email Alerts
Cited By
Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
ASME J of Nuclear Rad Sci (October 2023)
A Novel Algorithm for Fast Measurement of Material Density in Symmetrical Objects Using X-Ray Radiography
ASME J of Nuclear Rad Sci (July 2023)
ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
ASME J of Nuclear Rad Sci (October 2023)
Hydrogen Loading System for Thin Films for Betavoltaics
ASME J of Nuclear Rad Sci (October 2023)
Related Articles
Application of Fractional Scaling Analysis to Loss of Coolant Accidents, System Level Scaling for System Depressurization
J. Fluids Eng (August,2009)
Assessment of the Code “PTCREEP” for IPHWR Pressure Tube Ballooning Study
J. Pressure Vessel Technol (February,2011)
Study of the Convective Heat Transfer in a Rotating Coolant Channel
J. Turbomach (January,1989)
COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
ASME J of Nuclear Rad Sci (July,2016)
Related Proceedings Papers
Break Size Effects on CET Response in an Upper Head SBLOCA Transient
ICONE20-POWER2012
Related Chapters
Control and Operational Performance
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)