Break location influence in pressure vessel SBLOCA scenarios
DOI:
https://doi.org/10.15392/bjrs.v8i3B.712Keywords:
SBLOCA, AM actions, TRACEAbstract
The inspections performed in Davis Besse and in the South Texas Project Unit-I reactors pointed out safety issues regarding the structural integrity of the Pressure Vessel (PV). In these inspections, two anomalies were found: a wall thinning and degradation in the PV upper head of the Davis Besse reactor and a small amount of residue around of two instrument-tube penetration nozzles located in the PV lower plenum of the South Texas Project Unit-I reactor. The evolution of these defects could have resulted in Small Break Loss-Of-Coolant Accidents (SBLOCA) if they had not been detected in time. In this frame, the OECD/NEA considered the necessity to simulate these accidental sequences in the OECD/NEA ROSA Project using the Large Scale Test Facility (LSTF). This work is focused on simulating different hypothetical accidental scenarios in the PV using the thermal-hydraulic code TRACE5. These simulations allow studying the break localization influence in the transient and the effectiveness of the accident management (AM) actions considered mitigating the consequences of these hypothetical accidental scenarios.
Downloads
References
USNRC - United States Nuclear Regulatory Commission. Davis-Besse Reactor Pressure Vessel Head Degradation, Overview, Lessons Learned, and NRC Actions Based on Les-sons Learned. NUREG/BR-0353, Rev. 1, 2008.
QUERAL, C.; GONZÁLEZ-CADELO, J.; JIMENEZ, G.; VILLALBA, E. Accident Management actions in an upper-head Small-Break Loss-Of-Coolant accident with high-pressure safety injection failed. Nuclear Technology, v. 175 (3), p. 572-593, 2011.
Thermohydraulic Safety Research Group, Nuclear Safety Research Center, Quick-look Data Report of ROSA/LSTF Test 6-2 (0.1% Pressure Vessel Bottom Small Break LOCA Ex-periment SB-PV-10 in JAEA). Japan Atomic Energy Agency, JAEA, (2006).
The ROSA-V Group. ROSA-V Large Scale Test Facility (LSTF) System Descrip-tion for the 3rd and 4h Simulated Fuel Assemblies. JAERI-Tech, 2003.
Thermohydraulic Safety Research Group, Nuclear Safety Research Center. Final Data Report of ROSA/LSTF Test 6-1 (1.9% Pressure Vessel Upper-head Small Break LOCA Ex-periment SB-PV-09 in JAEA). Japan Atomic Energy Agency, JAEA, 2006.
FREIXA, J.; MANERA, A. Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE. Nuclear Engineering and Design, v. 240, p. 1779-1788, 2010.
GALLARDO, S.; ABELLA, V.; VERDÚ, G. Assessment of TRACE 5.0 Against ROSA Test 6-1, Vessel Upper Head SBLOCA. NUREG/IA-0245, 2010.
QUEROL, A.; GALLARDO, S.; VERDÚ, G. Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled Up Model. Jour-nal of Nuclear Engineering and Radiation Science, v. 2 (2), p. 1-6, 2016.
Division of Risk Assessment and Special Projects. Office of Nuclear Regulatory Research, U. S Nuclear Regulatory Commission. TRACE V5.0. Theory manual. Field Equations, Solution Methods and Physical Models. U. S. Nuclear Regulatory Commission, 2007.
Division of Risk Assessment and Special Projects. Office of Nuclear Regulatory Research, U. S. Nuclear Regulatory Commission. TRACE V5.0. User’s manual. Volume 1: Input Specification. U. S. Nuclear Regulatory Commission, 2007.
QUEROL, A.; GALLARDO, S.; VERDÚ, G. Intermediate BLOCA Scenarios. Sensi-tivity Analysis with TRACE5. Transactions of the American Nuclear Society, v. 106, p. 1049–1052, 2012.
QUEROL, A.; GALLARDO, S.; VERDÚ, G. Simulation of a SBLOCA in a Hot Leg. Scaling Considerations and Application to a Nuclear Power Plant. Nucl. Eng. Des., v. 283, p. 81–99, 2015.
CARLOS, S.; QUEROL, A.; GALLARDO, S.; SANCHEZ-SAEZ, F.; VILLANUE-VA, J. F.; MARTORELL, S.; VERDÚ, G. Post-test analysis of the ROSA/LSTF and PKL counter-part tests. Nucl. Eng. Des., v. 297, p. 81–94, 2016.
KUKITA, Y.; TASAKA, K.; ASAKA, H.; YONOMOTO, T.; KUMAMARU, H. The effects of break location on PWR small break LOCA: Experimental study at the ROSA-IV LSTF. Nuclear Engineering and Design, v. 122, p. 255-262, 1990.
Downloads
Published
Issue
Section
License
Copyright (c) 2021 Brazilian Journal of Radiation Sciences
This work is licensed under a Creative Commons Attribution 4.0 International License.
Licensing: The BJRS articles are licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons license, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons license and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/