Abstract

An experimental simulation for a loss of coolant accident with a 4 inch cold leg top-slot break was performed using ATLAS, an integral effect test facility at KAERI, Korea. The aims of this test are to resolve a safety issue and to validate the thermal hydraulic safety analysis codes for the activity of the 4th ATLAS-Domestic Standard Problem. The related safety issue for this test is that a loop seal clearing and loop seal reformation of APR1400 can lead to a core temperature excursion because of the characteristics of the loop seal geometry. In the experimental results, the core heater temperature slowly increased after loop seal reformation. This increase is attributed to the accumulated steam at the upper head. The accumulated steam increased the pressure and saturated the temperature in the core. The core heater temperature then increased due to the increased saturated temperature. This temperature increase therefore was not a core temperature excursion. Sensitivity analysis results using MARS-KS, which is a best-estimate thermal hydraulic system analysis code, are also presented in this study. In the 4th ATLAS-Domestic Standard Problem, 15 participants performed calculations and sensitivity analyses using various thermal hydraulic safety analysis codes (MARS-KS, SPACE, RELAP5, and TRACE). From this exercise, several parameters that affect the calculation results are brought out. The sensitivity analysis results using MARS-KS with some of these parameters are also presented. The MARS-KS calculation results are similar to the experimental data. The effects of critical flow model, break line modeling, and fine node modeling are also discussed.

Highlights

  • An issue of the APR1400 loop seal and its impact on long-term cooling during a postulated loss-of-coolant accident (LOCA) was raised (Lu, 2014)

  • The main feed water isolation valves were closed with the low pressurizer pressure (LPP) signal

  • The actuation of the safety injection pumps (SIPs) was set to occur with a 28-s delay from the LPP signal

Read more

Summary

INTRODUCTION

An issue of the APR1400 loop seal and its impact on long-term cooling during a postulated loss-of-coolant accident (LOCA) was raised (Lu, 2014). The APR1400 has a deeper loop seal, and the impact of the loop seal can be more serious than in other pressurized water reactors (PWRs) because the deeper loop seal necessitates longer time to clear the loop seal and partial core uncovery can occur during this time. A top-slot break scenario was simulated in ATLAS, an integral effect test facility. This experiment was aimed at investigating the thermal hydraulic transient in the top-slot break at the CL and analyzing the effect of the LSC and LSR on the APR1400. ATLAS is an integral effect test facility designed to simulate transient scenarios for thermal hydraulics of a PWR (Baek et al, 2005).

Transient Results of Experiment
CONCLUSION
DATA AVAILABILITY STATEMENT
Full Text
Paper version not known

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call

Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.