Title of article :
Controlling and cooling core melts outside the pressure vessel
Author/Authors :
Alsmeyer، H. نويسنده , , Tromm، W. نويسنده , , Albrecht، G. نويسنده , , Fieg، G. نويسنده , , Stegmaier، U. نويسنده , , Werle، H. نويسنده ,
Issue Information :
دوهفته نامه با شماره پیاپی سال 2000
Pages :
-268
From page :
269
To page :
0
Abstract :
For future reactors, the control and cooling of ex-vessel corium melts is under consideration to increase the passive safety features even for very unlikely severe accidents. In this context, different research activities are studying ex-vessel corium behaviour and control, including the implementation of a core cooling device outside the reactor pressure vessel in order to prevent basement erosion and to maintain the integrity of the containment. This paper describes current research on key phenomena which must be understood and quantified to be finally controlled by the cooling device. These are the release of corium melt from the pressure vessel, the temporary retention of the melt in the reactor cavity until melt through of the gate, spreading of the melt on a large surface, and finally the cooling and solidification of the melt by direct water contact. The experiments use high temperature melts which are similar to corium melts. Where necessary, models are developed to transfer the results to reactor scale.
Keywords :
Two-phase flow , Drift flow , BWR fuel spacer , Droplet deposition rate , Critical power , Annular mist flow , Liquid film , Phase Doppler anemometer
Journal title :
Nuclear Engineering and Design
Serial Year :
2000
Journal title :
Nuclear Engineering and Design
Record number :
13909
Link To Document :
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