抄録
The code RELAP5-3D is used for the analysis of a 0.5% cold-leg Small-Break Loss-of-Coolant Accident (SBLOCA) experiment PL-12 conducted at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility with the passive core cooling injection. The code predictions include the analysis for primary system pressure, loop flow rate, loop and CMT temperatures, coolant inventory distribution in pressurizer, Accumulator (ACC), and Core Makeup Tank (CMT), mass flow rate in Passive Residual Heat Removal (PRHR) system, and other core thermal-hydraulics. A comparison between the calculated results and the experiment data shows (a) a good match with the prediction of the primary system pressure, CMT-1 upper portion temperature, and loop-3 hot-leg fluid temperature, (b) underprediction of the loop-3 mass flow rate and CMT-1 lower portion temperature, (c) overprediction of the pressurizer liquid level, CMTs liquid level and PRHR system mass flow rate.
