IPC분류정보
국가/구분 |
United States(US) Patent
등록
|
국제특허분류(IPC7판) |
|
출원번호 |
US-0187000
(1988-04-27)
|
우선권정보 |
FR-0005936 (1987-04-27) |
발명자
/ 주소 |
- Martin Alain (Caluire FRX)
|
출원인 / 주소 |
- Framatome (Courbevoie FRX 03)
|
인용정보 |
피인용 횟수 :
11 인용 특허 :
3 |
초록
▼
The method consists in separating the worn-out steam generator (1) from the primary circuit, by sectioning the pipes (3, 5) in the vicinity of the steam generator pipework, withdrawing the worn-out steam generator, placing a replacement steam generator in position and welding the pipe work of the re
The method consists in separating the worn-out steam generator (1) from the primary circuit, by sectioning the pipes (3, 5) in the vicinity of the steam generator pipework, withdrawing the worn-out steam generator, placing a replacement steam generator in position and welding the pipe work of the replacement steam generator to the primary pipes (3, 5). Topometric measurements are carried out on the replacement generator, on the worn-out steam generator (1) in position in its compartment (11) and in the compartment (11) after the removal of the worn-out generator (1). Comparison of the topometric measurements enables the replacement procedure to be determined, i.e., the number of cuts to be made on the primary pipes (3, 5), the modifications to be made to the supporting and positioning devices (8, 17) and the position of the chamfers for welding the pipes (3, 5) and the pipework of the replacement steam generator.
대표청구항
▼
In a method for the complete replacement of a worn-out steam generator (1) of a pressurized water nuclear reactor comprising a reactor building (10) defining a compartment (11) in which the steam generator (1) is retained in a specified position by means of supporting and positioning devices (8, 17)
In a method for the complete replacement of a worn-out steam generator (1) of a pressurized water nuclear reactor comprising a reactor building (10) defining a compartment (11) in which the steam generator (1) is retained in a specified position by means of supporting and positioning devices (8, 17) placed in said compartment, and a primary circuit (3, 4, 5) in said reactor building (10) in which primary circuit pressurized water circulates, said primary circuit comprising two pipes (3,5) connected to a lower part of said worn-out steam generator (1) in the region of corresponding nozzles of said worn-out steam generator, said method comprising the steps of separating said worn-out steam generator (1) from said primary circuit by sectioning said pipes (3, 5) in the vicinity of pipework of said worn-out steam generator (1), withdrawing said worn-out steam generator from said compartment (11), placing a replacement steam generator (20) in position in said compartment (11) and welding the nozzles (22a, 22b) of said replacement steam generator to said pipes (3, 5), in the region of welding chamfers, the improvement comprising the steps of (a) carrying out topometric measurements on said replacement steam generator (20) to determine exactly the position of supporting and positioning parts (25) of said replacement steam generator intended to come to bear on said supporting and positioning devices (8, 17) of said compartment (11) and the geometry of said nozzles (22a, 22b) for connection to said primary circuit (3, 5); (b) carrying out topometric measurements in said compartment (11) and on said worn-out steam generator (1) to determine the geometry of said connection to said primary circuit (3, 5) and of said supporting and positioning devices (8, 17) of said compartment; (c) comparing topometric measurements carried out to determine the number and the position of the sectioning operations to be carried out on said pipes (3, 5) of said primary circuit, and modifications to be made to the supporting and positioning devices (8, 17) of said compartment, for positioning said replacement steam generator (20); (d) carrying out sectioning operations and withdrawal of said worn-out steam generator (1) from said compartment (11), and grinding the sectioned surfaces on said pipes (3, 5) of said primary circuit; (e) carrying out topometric measurements in said compartment (11) after withdrawal of said worn-out steam generator (11), to determine the exact position of said supporting and positioning devices (8, 17) of said compartment and of sectioned ends of said pipes (3, 5) of said primary circuit; (f) verifying the feasibility of employing the replacement procedure by comparison of the measurements carried out; (g) determining the exact position of the welding chamfers on the ends of the primary pipes (3, 5); and (h) machining corresponding chamfers, placing said replacement steam generator (20) and its supporting and positioning devices in position and performing the welding connection of said nozzles (22a, 22b) and of said pipes (3, 5).
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