B204 EVALUATION OF THE KNGR DIRECT VESSEL SAFETY INJECTION SYSTEM FOR A LARGE BREAK LOCA USING MARS 1.4(Nuclear power-2)

概要

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To identify the thermal-hydraulic phenomena that are likely to occur during a large, cold leg break LOCA for a Korean Next Generation Reactor (KNGR), a Phenomena Identification and Ranking Table (PIRT) for the DVI ECCS is developed and an ECCS performance evaluation using the best-estimate code MARS 1.4 has been carried out. The KNGR is a 4000 MWt advanced light water reactor adopting four mechanically separated hydraulic trains of Direct Vessel Injection (DVI) ECCS. The PIRT results show that the 3D flow distribution in the downcomer during a large break LOCA is the most important phenomenon to be observed. The ECCS performance analysis results employing the conservative assumptions show that the KNGR ECCS provides sufficient coolant to properly quench the core. These PIRT and analysis results are used to provide the reference conditions and guidance for the KNGR DVI ECCS performance test, which is in progress at KAERI.
一般社団法人日本機械学会の論文
2000-10-01