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Thermal-Hydraulics of Water Cooled Nuclear Reactors by Francesco D'Auria

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6.4.3 Thermal-hydraulic phenomena for integral facilities of VVERs

In addition, to set-up validation matrices for Russian Pressurized Water-cooled and Water-moderated Energy Reactor (WWER or VVER) analyses, an international Working Group was formed on the initiative of the Federal Ministry for Research and Technology (BMFT) of the Federal Republic of Germany. A further evaluation of the WWER matrices was performed by a CSNI Support Group. Based on these CSNI matrices the lists of phenomena have been reviewed and adopted to the characteristics of WWER-440 and WWER-1000 systems, respectively.

Germany, Hungary, Russia, Slovak Republic, Poland, and Ukraine has been formed on the initiative of the BMFT of the Federal Republic of Germany, giving the ...

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