The licensing is a legal process to transfer the nuclear safety technology (developed and supported by researches) into a legal-fixed environment. Competences in the legal nuclear safety framework (typically part of the Atomic Act in each Country) and of nuclear reactor safety are needed in such a context. VVER-1000 (Water-Cooled, Water-moderated, Energy Reactor,1000 Mwe) designed in Russia (former Soviet Union) went in operation in Russia and in former Soviet Union satellite Countries plus (recently) India, China and Iran. VVER-1000 is equipped with four horizontal tubes steam generators. The core consists of approximately 4 m high fuel rods arranged in a hexagonal fuel bundles with a triangular pitch. University of Pisa pioneered the effort of analyzing the transient performance and the safety of those reactors. The present document deals with accident analysis, in particular the Large Break Loss of Coolant (LBLOCA) scenario, in the Bulgarian Kozloduy reactor No 5. The results were used for training of one of the authors and for confirming the safety margins of the reactor.
Consistent code/nodalization qualification processes and application to VVER-1000 NPP
D’Auria FrancescoPenultimo
;
2005-01-01
Abstract
The licensing is a legal process to transfer the nuclear safety technology (developed and supported by researches) into a legal-fixed environment. Competences in the legal nuclear safety framework (typically part of the Atomic Act in each Country) and of nuclear reactor safety are needed in such a context. VVER-1000 (Water-Cooled, Water-moderated, Energy Reactor,1000 Mwe) designed in Russia (former Soviet Union) went in operation in Russia and in former Soviet Union satellite Countries plus (recently) India, China and Iran. VVER-1000 is equipped with four horizontal tubes steam generators. The core consists of approximately 4 m high fuel rods arranged in a hexagonal fuel bundles with a triangular pitch. University of Pisa pioneered the effort of analyzing the transient performance and the safety of those reactors. The present document deals with accident analysis, in particular the Large Break Loss of Coolant (LBLOCA) scenario, in the Bulgarian Kozloduy reactor No 5. The results were used for training of one of the authors and for confirming the safety margins of the reactor.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
