Title of article :
Analyses of PACTEL passive safety injection experiments with APROS, CATHARE and RELAPS codes
Author/Authors :
Tuunanen، Jari نويسنده , , Vihavainen، Juhani نويسنده , , DAuria، Francesco نويسنده ,
Issue Information :
دوهفته نامه با شماره پیاپی سال 2000
Abstract :
The European Commission fourth framework programme project ʹAssessment of passive safety injection systems of advanced light water reactorsʹ involved experiments on the PACTEL test facility and computer simulations of selected experiments. The experiments focused on the performance of passive safety injection systems (PSIS) of advanced light water reactors (ALWRs) in small break loss-of-coolant accident (SBLOCA) conditions. The PSIS consisted of a core make-up tank (CMT) and two pipelines. A pressure balancing line (PBL) connected the CMT to one cold leg. The injection line (IL) connected it to the downcomer. The project involved 15 experiments in three series. The experiments provided information about condensation and heat transfer processes in the CMT, thermal stratification of water in the CMT, and natural circulation flow through the PSIS lines. The project included validation of three thermal-hydraulic computer codes (APROS, CATHARE and RELAP5). The analyses showed the codes are capable of simulating the overall behaviour of the transients. The codes predicted accurately the core heatup, which occurred when the primary coolant inventory was reduced so much that the core top became free of water. The detailed analyses of the calculation results showed that some models in the codes still need improvements. Especially, further development of models for thermal stratification, condensation and natural circulation flow with small driving forces would be necessary for accurate simulation of the phenomena in the PSIS.
Keywords :
Boiling water reactors , Hydrogen management , Overpressure protection
Journal title :
Nuclear Engineering and Design
Journal title :
Nuclear Engineering and Design