Abstract
Several three-dimensional hexagonal reactor dynamic codes
have been developed for VVER type reactors and coupled
with different thermal-hydraulic system codes. Under the
auspices of the European Union's Phare programme these
codes have been validated against real plant transients
by the participants from 7 countries. Two of the
collected five transients were chosen for validation of
the codes. Part 1 of this article consists of validation
against VVER-1000 reactor data. This second part is
focussed to validation against measured data of `One
turbo-generator load drop experiment' at the Loviisa-1
VVER-440 reactor. The experiment was performed just after
plant modernisation and more measured data was available
to validation than in normal operation of real plants.
Good accuracy of the results was generally achieved
comparable to the measurement accuracy. The confidence in
the results of the different code systems has increased,
and consequences of certain model changes could be
evaluated.
Original language | English |
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Pages (from-to) | 255-269 |
Journal | Annals of Nuclear Energy |
Volume | 29 |
Issue number | 3 |
DOIs | |
Publication status | Published - 2002 |
MoE publication type | A1 Journal article-refereed |
Keywords
- accident modelling
- field test
- genetically modified organism
- GMHAZID
- risk assessment method
- hazard identification
- plants
- research articles
- risk analysis
- risk evaluation
- systematic hazard identificatione