Abstract
The European Commission fourth framework programme project ‘Assessment
of passive safety injection systems of advanced light water reactors’
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.
| Original language | English |
|---|---|
| Pages (from-to) | 261-286 |
| Journal | Nuclear Engineering and Design |
| Volume | 198 |
| Issue number | 3 |
| DOIs | |
| Publication status | Published - 2000 |
| MoE publication type | A1 Journal article-refereed |
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