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AssigneeFramatome
InventorsJean Damezin, Guy Desfontaines, Jean-Paul Millot
Estimating the term…
The device comprises a mobile probe which can be displaced inside thimbles. A plurality of ducts (20) for the passage and support of a thimble are disposed in the partitioning (6) of the reactor, around the core (4) along an axial direction and substantially over the entire height of the core. The ducts (20) are distributed circumferentially around the core (4). A plurality of feed-through sleeves in the cover of the vessel are each disposed along the axial extension of a duct (20) for the passage of a thimble. Guide columns each disposed along the axial extension of a duct and each engaged in a feed-through sleeve in the cover of the vessel form, with the corresponding duct (20) and feed-through sleeve, a channel for the reception of a thimble. An arrangement for the guidance, displacement, switching and parking of the mobile probe is disposed outside the vessel (1) and fixed on to the cover of the vessel. This arrangement comprises a plurality of guide tubes each connected at one of its ends to the apparatus for displacement, guidance and switching of the mobile probe and, at its other end, to a thimble. The device with mobile probe enables a readjustment to be carried out to the measurements of neutron flux made by a set of fixed instruments comprising in particular external multi-stage fission chambers (40).
Device for measuring the neutron flux in the core (4) of a nuclear reactor comprising a vessel (1) of generally cylindrical shape having a vertical axis and enclosing the reactor core (4), a primary circuit for the circulation of the reactor coolant comprising at least one loop in communication with an internal volume of the vessel, partitioning (6) surrounding the core inside the vessel (1) and a cover (3) closing an upper part of the vessel (1), the measuring device consisting of at least one probe (52) movable inside at least one thimble (25) for measuring the neutron flux in the reactor core (4), said device further comprising:
Method for the measurement of the neutron flux in the core (4) of a nuclear reactor comprising a vessel (1) of cylindrical shape having a vertical axis and enclosing the reactor core (4), partitioning (6) surrounding the core (4) inside the vessel (1), a cover (3) closing the vessel (1) at its upper part, tubular sleeves (21, 48) passing through the cover (3) of the vessel (1), control rods mounted in at least one part of the sleeves (48) in order to be guided in these sleeves and to ensure the displacement in the core (4) of absorbent control clusters, fixed to the control rods, for the control of the reactivity of the core (4) and at least one primary loop connected to the vessel (1) in which primary coolant of the reactor circulates, said method comprising the steps of:
Dependencies are inferred from the claim text.