[미국특허]
Space saver flanged joint for a nuclear reactor vessel
원문보기
IPC분류정보
국가/구분
United States(US) Patent
등록
국제특허분류(IPC7판)
G21D-001/00
G21C-015/243
출원번호
US-0398946
(2013-05-06)
등록번호
US-9892806
(2018-02-13)
국제출원번호
PCT/US2013/039743
(2013-05-06)
국제공개번호
WO2013/188018
(2013-12-19)
발명자
/ 주소
Singh, Krishna P.
Rajkumar, Joseph
출원인 / 주소
SMR INVENTEC, LLC
대리인 / 주소
The Belles Group, P.C.
인용정보
피인용 횟수 :
0인용 특허 :
14
초록▼
A nuclear steam supply system includes an elongated reactor vessel having an internal cavity with a central axis, a reactor core having nuclear fuel disposed within the internal cavity, and a steam generating vessel having at least one heat exchanger section, the steam generating vessel being fluidi
A nuclear steam supply system includes an elongated reactor vessel having an internal cavity with a central axis, a reactor core having nuclear fuel disposed within the internal cavity, and a steam generating vessel having at least one heat exchanger section, the steam generating vessel being fluidicly coupled to the reactor vessel. The reactor vessel includes a shell having an upper flange portion and a head having a head flange portion. The upper flange portion is coupled to the head flange portion, wherein the upper flange portion extends into the internal cavity, and the head flange portion extends outward from the internal cavity. Primary coolant flow between the steam generating vessel and reactor vessel occurs via a fluid coupling comprising direct welding between forged outer nozzles of each vessel and welded inner nozzles between each vessel inside the outer nozzles.
대표청구항▼
1. A nuclear steam supply system comprising: an elongated reactor vessel having an internal cavity with a central axis, the reactor vessel comprising a shell, having a first shell portion and an upper flange portion, a head, having a head flange portion, the upper flange portion being coupled to the
1. A nuclear steam supply system comprising: an elongated reactor vessel having an internal cavity with a central axis, the reactor vessel comprising a shell, having a first shell portion and an upper flange portion, a head, having a head flange portion, the upper flange portion being coupled to the head flange portion, and a primary coolant first flow nozzle, having a first outer nozzle formed as a forging with the reactor vessel and a first inner nozzle inside the first outer nozzle;a reactor core comprising nuclear fuel disposed within the internal cavity; anda steam generating vessel comprising at least one heat exchanger section and a primary coolant second flow nozzle, having a second outer nozzle formed as a forging with the steam generating vessel and a second inner nozzle inside the second outer nozzle, wherein the second outer nozzle is directly welded to the first outer nozzle without any intervening piping sections, and the second inner nozzle is directly welded to the first inner nozzle;a plurality of circumferentially arranged longitudinal bores formed in the upper flange portion of the shell and the head flange portion of the head, wherein a first distance between each bore and central axis of the internal cavity of the reactor vessel is less than a second distance between the central axis and an outer surface of the first shell portion of the reactor vessel. 2. The nuclear steam supply system of claim 1 wherein the elongated reactor vessel includes a plurality of support flanges projecting outward from the shell and collectively configured to support the elongated reactor vessel, wherein the first outer nozzle extends radially outward from the shell a distance that is not more than a radial projection of the support flanges. 3. The nuclear steam supply system of claim 1 wherein the second outer nozzle is butt welded to the first outer nozzle, and the second inner nozzle is butt welded to the first inner nozzle. 4. The nuclear steam supply system of claim 1 wherein the upper flange portion extends into the internal cavity, the head flange portion extends outward from the internal cavity, and an inner surface of the head flange portion is disposed closer to the central axis than an inner surface of the first shell portion along respective parallel radial lines extending from the central axis. 5. The system according to claim 4 wherein the first shell portion has a first inner radius, and the head flange portion has a second inner radius, which is smaller than the first inner radius. 6. The system according to claim 4 wherein the first shell portion has an inner radius, and the head flange portion has an outer radius, which is smaller than or equal to the inner radius. 7. The system according to claim 4 wherein the first shell portion has a first inner surface, and the head flange portion has a second inner surface, and wherein the second inner surface is closer to the central axis than the first inner surface along respective parallel radial lines extending from the central axis. 8. The system according to claim 4 wherein the shell includes a first inner surface and a second inner surface, and wherein the second inner surface is closer to the central axis than the first inner surface along respective parallel radial lines extending from the central axis. 9. The system according to claim 4 wherein the first shell portion has an inner surface, and the head flange portion has an outer surface, and wherein the outer surface is at least as close to the central axis as the inner surface along respective parallel radial lines extending from the central axis.
Tower Stephen N. (Washington Township ; Westmoreland County PA) Veronesi Luciano (O\Hara Township ; Allegheny County PA) Currey Charles F. (Wilkins Township ; Allegheny County PA), Compact small pressurized water nuclear power plant.
Badoux Jean-Paul (Le Puy Sainte FRX) Chaix Jean E. (Pierrevert FRX) Metteey Michel (Eguilles FRX), Steam generator, particularly for pressurized water nuclear reactor.
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