Patent classifications
G21C13/036
Nuclear reactor, guide tube support, and corresponding maintenance method
A nuclear reactor includes guide tubes; and vessel head penetrations each comprising a tubular adapter fixed in one of the openings and defining an inner passage. Each vessel head penetration also includes a tubular sleeve engaged in the inner passage and axially extending in line with one of the guide tubes. Each sleeve is suspended by an upper axial sleeve end lying on an upper range on the corresponding adapter. A lower axial end of the sleeve projects axially into the vessel beyond the adapter and is separated from an upper axial end of the corresponding guide tube by an axial gap having an axial height of less than 50 millimeters.
Nuclear reactor, guide tube support, and corresponding maintenance method
A nuclear reactor includes guide tubes; and vessel head penetrations each comprising a tubular adapter fixed in one of the openings and defining an inner passage. Each vessel head penetration also includes a tubular sleeve engaged in the inner passage and axially extending in line with one of the guide tubes. Each sleeve is suspended by an upper axial sleeve end lying on an upper range on the corresponding adapter. A lower axial end of the sleeve projects axially into the vessel beyond the adapter and is separated from an upper axial end of the corresponding guide tube by an axial gap having an axial height of less than 50 millimeters.
Method and device for replacing sleeves lining nuclear reactor pressure vessel tubes
A method for restraining a sleeve lining a tube passing through a nuclear reactor pressure vessel is provided. The method includes attaching in situ a radial protrusion on an external surface of the sleeve; and attaching a collar to an end of the tube and coupling the radial protrusion with the collar to retain the thermal sleeve in position.
Method and device for replacing sleeves lining nuclear reactor pressure vessel tubes
A method for restraining a sleeve lining a tube passing through a nuclear reactor pressure vessel is provided. The method includes attaching in situ a radial protrusion on an external surface of the sleeve; and attaching a collar to an end of the tube and coupling the radial protrusion with the collar to retain the thermal sleeve in position.
NUCLEAR REACTOR HEAD, NUCLEAR REACTOR COMPRISING SUCH A NUCLEAR REACTOR HEAD AND METHOD OF MAINTAINING A NUCLEAR REACTOR
A nuclear reactor head (12) comprising a vessel top head (14), a penetration (36) extending through the vessel top head (14) along a penetration axis (B) for allowing passage of a control shaft (34) of a control rod drive mechanism (32) through the vessel top head (14) and to a corresponding control guide tube (30) of the nuclear reactor (2), the penetration (36) comprising a penetration tube (38) extending through the vessel top head (14) and a thermal sleeve (40) extending inside the penetration tube (38) and coaxially with the penetration tube (38) with an axial play between the thermal sleeve (40) and the penetration tube (38), wherein the nuclear reactor head further comprises a spacer (60) attached to a lower end of the thermal sleeve (40) for maintaining minimal spacing with the upper end of the corresponding control rod guide tube (30).
NUCLEAR REACTOR HEAD, NUCLEAR REACTOR COMPRISING SUCH A NUCLEAR REACTOR HEAD AND METHOD OF MAINTAINING A NUCLEAR REACTOR
A nuclear reactor head (12) comprising a vessel top head (14), a penetration (36) extending through the vessel top head (14) along a penetration axis (B) for allowing passage of a control shaft (34) of a control rod drive mechanism (32) through the vessel top head (14) and to a corresponding control guide tube (30) of the nuclear reactor (2), the penetration (36) comprising a penetration tube (38) extending through the vessel top head (14) and a thermal sleeve (40) extending inside the penetration tube (38) and coaxially with the penetration tube (38) with an axial play between the thermal sleeve (40) and the penetration tube (38), wherein the nuclear reactor head further comprises a spacer (60) attached to a lower end of the thermal sleeve (40) for maintaining minimal spacing with the upper end of the corresponding control rod guide tube (30).
Replacement thermal sleeve for a reactor vessel closure head penetration adapter of control rod drive mechanism
A replacement thermal sleeve with a flange for a reactor vessel closure head penetration adapter housing. By altering a diameter of the flange, a replacement thermal sleeve can be installed through the narrow diameter of the penetration adapter housing opening from under the reactor vessel head. The flange can be compressible or expandable or the tubular wall of the thermal sleeve can be inserted in longitudinal sections, one at a time, into an opening in the underside of the penetration head adapter and reformed within the opening when fully inserted.
Replacement thermal sleeve for a reactor vessel closure head penetration adapter of control rod drive mechanism
A replacement thermal sleeve with a flange for a reactor vessel closure head penetration adapter housing. By altering a diameter of the flange, a replacement thermal sleeve can be installed through the narrow diameter of the penetration adapter housing opening from under the reactor vessel head. The flange can be compressible or expandable or the tubular wall of the thermal sleeve can be inserted in longitudinal sections, one at a time, into an opening in the underside of the penetration head adapter and reformed within the opening when fully inserted.
Method of peening an obstructed region of a metal assembly
A method for peening an obstructed region of a metal assembly that is obstructed by an obstructing part of the metal assembly is provided. The method includes determining an optimal peening path for treating the obstructed region irrespective of the obstructing part; identifying a portion of the obstructing part within the optimal peening path; determining a section of the portion of the obstructing part that is removable without affecting a mechanical integrity and functionality of the obstructing part; removing, by machining, the section so as to create additional space along the optimal peening path; and peening the obstructed region, a path of the peening at least partially crossing through the additional space. A method for peening a nuclear reactor pressure vessel is also provided.
Method of peening an obstructed region of a metal assembly
A method for peening an obstructed region of a metal assembly that is obstructed by an obstructing part of the metal assembly is provided. The method includes determining an optimal peening path for treating the obstructed region irrespective of the obstructing part; identifying a portion of the obstructing part within the optimal peening path; determining a section of the portion of the obstructing part that is removable without affecting a mechanical integrity and functionality of the obstructing part; removing, by machining, the section so as to create additional space along the optimal peening path; and peening the obstructed region, a path of the peening at least partially crossing through the additional space. A method for peening a nuclear reactor pressure vessel is also provided.