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Yang S.,State Nuclear Power Technology Research and Development Center South Area | Lu W.,State Nuclear Power Technology Research and Development Center South Area | Hu T.,State Nuclear Power Technology Research and Development Center South Area | Chang H.,State Nuclear Power Technology Research and Development Center South Area
International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 | Year: 2015

In-vessel retention of molten corium through external reactor vessel cooling (IVR-ERVC) is a severe accident management strategy. The effectiveness of IVR-ERVC strongly depends on the critical heat flux (CHF). This study conducted CHF experiments using the FIRM facility, which is a 2-D large scale model with SA508 steel as the heated surface material, to investigate the effects of coolant additives including boric acid (BA: H3BO5) or/and trisodium phosphate (TSP: Na3P04) on the CHF behaviors. Preliminary results were obtained. The CHF of BA was reduced compared with that of DI water because of the loose, irregular Fe^O^ oxide layer formed on the heated surface and the reduction was 4.1 % for the case of using BA 3000ppm.The CHF for TSP solution with lower concentration of lOOOppm was enhanced by 4.0%, which is mainly due to the increase wettability of coolant. However, a CHF reduction of 6.4% is observed for the case of using TSP with a much higher concentration of 3500ppm caused by the increase of two phase flow instability by the surfactant with high concentration under high mass flow condition. The CHF values for the mixed solution of CHF and TSP showed the same variation trend with that of the TSP solution, which indicates the TSP has a dominated effect on the CHF behavior. In addition, it suggests the coolant which contains BA and TSP with certain concentration could provide additional thermal margin for the IVR-ERVC strategy. Source

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