Heat Transfer Calculation of core melt diluted by oxide sacrificial material during in-vessel retention
Creators
- 1. State Nuclear Power Technology R and D Center, Beijing (China)
Description
Diluting the core melt with oxide sacrificial material (OSM) during in-vessel retention (IVR) is a newly proposed severe-accident-management strategy of advanced LWRs. When severe accident occurs, the relocated core melt is diluted by OSM, resulting in the inverse stratification of melt pool configuration. Therefore, the researches on the calculations of heat transfer of melt pool are essential to optimize the component of OSM and evaluate the effectiveness of the strategy. The heat flux on the vessel outer surface after diluting the core melt with Fe3O4, TiO2 and Al2O3, respectively was calculated. The results show that the structure of upper plenum will melt due to the intense heat radiation after OSM is used. The maximum heat flux on the vessel outer surface reduces with the increase of OSM. When the volume of the OSM ceramics reaches 15 m3, the reactor vessel length should be increased by approximately 2 m. In this case, the heat flux reduces about 45% compared to the reactors without OSM. Moreover, the reduction of heat flux is most pronounced as Fe3O4 is used. In addition, the melting point of UO2-ZrO2-OSM affects the appearance of a crust on the surface of the oxide mixture, which in turn influences the maximum heat flux on the vessel outer surface. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 47
- Journal Issue
- 8
- Journal Page Range
- p. 1348-1355
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 46132176
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ACCIDENT MANAGEMENT; ALUMINIUM OXIDES; CERAMICS; COMPARATIVE EVALUATIONS; FERRITES; HEAT FLUX; HEAT TRANSFER; IRON OXIDES; MELTING POINTS; MIXTURES; PONDS; REACTOR ACCIDENTS; REACTOR VESSELS; RETENTION; STRATIFICATION; TITANIUM OXIDES; URANIUM DIOXIDE; ZIRCONIUM OXIDES
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALUMINIUM COMPOUNDS; CHALCOGENIDES; CONTAINERS; DISPERSIONS; ENERGY TRANSFER; EVALUATION; FERRIMAGNETIC MATERIALS; IRON COMPOUNDS; MAGNETIC MATERIALS; MANAGEMENT; MATERIALS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; SURFACE WATERS; THERMODYNAMIC PROPERTIES; TITANIUM COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; TRANSITION TEMPERATURE; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- 8 figs., 1 tabs., 11 refs.