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-440 (Water-Cooled, Water-moderated, Energy Reactor, 440 Mwe) designed in Russia (former Soviet Union) went in operation in Russia and in former Soviet Union satellite Countries with the noticeable exception of two units in Finland (and four units never started in Cuba). VVER-440 is equipped with six horizontal tubes steam generators. The core consists of approximately 2 m high fuel rods arrange in 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 (the Large Break Loss of Coolant (LBLOCA) scenario) in the Slovak Mochovce reactor No 3.
Qualification and uncertainty evaluation of a best estimate LOCA study of the (VVER-440) Mochovce NPP by Relap5/3.2-gamma
D’Auria F.
Primo
Conceptualization
;
2004-01-01
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-440 (Water-Cooled, Water-moderated, Energy Reactor, 440 Mwe) designed in Russia (former Soviet Union) went in operation in Russia and in former Soviet Union satellite Countries with the noticeable exception of two units in Finland (and four units never started in Cuba). VVER-440 is equipped with six horizontal tubes steam generators. The core consists of approximately 2 m high fuel rods arrange in 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 (the Large Break Loss of Coolant (LBLOCA) scenario) in the Slovak Mochovce reactor No 3.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
