Title of article :
Accident analyses and passive measures reducing the consequences of a core-melt in CAPRA/CADRA reactor cores
Author/Authors :
Maschek، W. نويسنده , , Struwe، D. نويسنده ,
Issue Information :
دوهفته نامه با شماره پیاپی سال 2000
Pages :
-310
From page :
311
To page :
0
Abstract :
As part of the Combustion Amelioree du Plutonium dans les Reacteurs Avances/Consommation DʹActinides et de Dechets dans les Reacteurs Avances (CAPRA/CADRA) program the feasibility of reactor systems with different neutron spectra and coolants is investigated to burn plutonium and also to destruct minor actinides and long lived fission products. In this paper, we deal with reactor cores with fast spectrum and metal cooling. The design of this type of CAPRA/CADRA cores shows significant differences compared e.g. to conventional fast reactor cores. The high Pu-enrichment and the high minor actinide load have an important influence on the core meltdown behavior and the associated recriticality risk. To cope with this risk, inherent design features and special measures/devices are investigated for their potential of early fuel discharge to reduce the criticality of the reactor core. An assessment of such measures/devices, which could provide an additional line of defense against severe accident development, is given. Within the CAPRA/CADRA program, also accelerator driven subcritical systems are investigated for performing the task of transmutation and incineration. In these fast neutron systems with a strong external neutron source, the kinetic behavior is different to a critical core and new strategies and measures for accident prevention have to be investigated.
Keywords :
Liquid film , Two-phase flow , Phase Doppler anemometer , Annular mist flow , Drift flow , Droplet deposition rate , Critical power , BWR fuel spacer
Journal title :
Nuclear Engineering and Design
Serial Year :
2000
Journal title :
Nuclear Engineering and Design
Record number :
13911
Link To Document :
بازگشت