Simulation of SBLOCA in RD-14M Test Facility using Computer Code MARS_KS
This paper presents the assessment results on the small inlet header break experiments which are performed in RD-14M test facility using MARS_KS (Multi-demensional Analysis for Reactor Safety) computer code. The RD-14M is 11MW, full elevation scaled thermal hydraulic test facility processing most of the key components of a CANDU (CANada Deuterium Uranium) primary heat transport system. Two RD-14M tests,, which were carried out for the simulation of small break LOCA (B9006) and steam generator condensation (B9802), were modeled and simulated using MARS_KS. MARS_KS code has been developed for a realistic analysis of thermal hydraulics transients in pressurized water reactors. Some important models for CANDU characteristics e.g. Critical flow model, nuclear kinetics model, critical heat flux model, valve and spray model, improvement of horizontal flow regime map, heat transfer model in horizontal channel, have been modified and applied to original MARS code. Through the both simulation results of B9006 and B9802, it is provided that MARS_KS code reasonably predicts main phenomena during the transient such as the ECC flow injection, pump discharge flow, void fraction in the system and primary pressure, etc. However, the FES temperature trend along the heated section 13 shows disagreement between experimental data and calculated results in test 9802. This might be due to a deficiency in the relevant models of MARS_KS code. Therefore, further works on the heat transfer model and flow regime model in the horizontal channel are required to reduce the code prediction uncertainties.
RD-14M MARS_KS SBLOCA CANDU SG Condensation
Joosung Kim Kap Kim Kwangwon Seul
Korea Institute of Nuclear Safety 19 Gueseong, Yuseong, Daejeon, Korea, 305-338
国际会议
上海
英文
2252-2262
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）