会议专题

Experimental Results on the Coolability of a Debris Bed with Down Comer Configurations

In case of a severe accident, a debris bed is formed from a mixture of molten core and the residual water in the lower plenum of the reactor pressure vessel. The presence of decay heat in a debris bed poses a critical threat to the reactor pressure vessel. To avoid any damage to the reactor pressure vessel the removal of decay heat from the debris bed is of great importance. In order to investigate experimentally the long-term coolability of debris beds, the non-nuclear test facility “DEBRIS has been established at IKE. Experimental investigations of coolability limits for such a debris bed, based on two different bed configurations and at various thermo-hydraulic conditions, are carried out at IKE. This paper presents the experimental results for multidimensional cooling effects on boiling and dryout tests with different bed configurations and different system pressures. Two different configurations, cylindrical and perforated cylindrical tube (down comer) with inner diameters 10 mm each, are used to investigate the multidimensional cooling effects. The down comer is concentrically installed inside the debris bed which itself is formed in a cylindrical crucible with an inner diameter of 125 mm. Different bed configurations, e. G. Polydispersed bed with spherical particles 2, 3 and 6 mm in diameters and irregular particles of equivalent diameters 2-10 mm, have been used with a bed height of 640 mm. A layer of ceramic balls of diameter 4 mm with a porosity of 40 % is used to make up a water pool at the bottom of the bed. The bottom inflow via the down comer tube as well as the lateral inflow of water through the perforated down comer tube into the bed improves the coolability of the debris bed, and therefore an increase in the dryout heat flux can be observed. Experimental results also show that the system pressure has no significant effect on the pressure gradient inside the bed, whereas with increasing system pressure the coolability limits are increased.

Pressure drop dryout heat flux coolability debris bed reactor safety

M. Rashid R. Kulenovic E. Laurien

IKE University of Stuttgart Pfaffenwaldring 31, 70569, Stuttgart, Germany

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

1874-1884

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)