CN203272395U - Fixed-pitch threaded rod looseness preventing structure of pressurized water reactor nuclear power plant vapor generator - Google Patents
Fixed-pitch threaded rod looseness preventing structure of pressurized water reactor nuclear power plant vapor generator Download PDFInfo
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- CN203272395U CN203272395U CN 201320203348 CN201320203348U CN203272395U CN 203272395 U CN203272395 U CN 203272395U CN 201320203348 CN201320203348 CN 201320203348 CN 201320203348 U CN201320203348 U CN 201320203348U CN 203272395 U CN203272395 U CN 203272395U
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- fixed
- screw rod
- spacing screw
- pitch threaded
- threaded rod
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Abstract
The utility model belongs to a vapor generator design technology, and particularly discloses a fixed-pitch threaded rod looseness preventing structure of a pressurized water reactor nuclear power plant vapor generator. The fixed-pitch threaded rod looseness preventing structure comprises a pipe locating plate and a plurality of fixed-pitch threaded rods. Arc-shaped grooves are machined in the fixed-pitch threaded rods. Rectangular sunk holes are machined in the pipe locating plate. Locking gaskets are arranged inside the rectangular sunk holes. The lower fixed-pitch threaded rod is fixedly connected with the upper fixed-pitch threaded rod through threads. Due to the fact that the arc-shaped grooves are machined in the fixed-pitch thread rods, when the fixed-pitch threaded rods and a pipe bearing plate are installed, the adopted locking gaskets can be compressed inside the arc-shaped grooves, the fixed-pitch threaded rods cannot be loosened or disengaged inside the pipe bearing plate and looseness and disengagement are prevented. Due to the fact that an end portion nut is installed on the upmost fixed-pitch threaded rod and arc-shaped grooves and tooth-shaped grooves are formed in the outer side of the nut, the upmost fixed-pitch threaded rod can be prevented from being loosened and disengaged, and meanwhile, due to the fact that the tooth-shaped grooves are machined, the end portion nut is also convenient to screw.
Description
Technical field
The utility model belongs to the steam generator designing technique, is specifically related to a kind of anti-loose structure about steam generator.
Background technique
The typical vertical natural recirculating type steam generator of pressurized-water reactor nuclear power plant is being furnished with some blocks of pipe support plates along restraining on straight length.
Common, 1 of two blocks of pipe support plate, 2 pairs of pipe support plates 1 of spacing screw rod being set provides supporting fixing, and bottom 1 of pipe support plate is connected to (as Fig. 1) on tube sheet by spacing screw rod 2.Between adjacent spacing screw rod, be between spacing screw rod and tube sheet and be threaded.The locking problem that the spacing screw flight connects just becomes the critical problem of spacing screw design.
In addition, the kilowatt pressurized water reactor nuclear power station steam generator that certain is in-service, the spacing screw rod of its use adopt screw thread to interconnect.As shown in Figure 2, at pipe support plate place topmost, adopt double nut to add the pin form locking.The locking designing requirement of this form is carried out the scene and is joined brill when the pipe support plate is installed, and need to carry out Site Welding.
There is following shortcoming in above-mentioned two kinds of spacing screw rods: due to steam generator secondary side to turbidity test require highly, on-the-spot processing (as boring, welding etc.) may cause the pollution to steam generator; Only be provided with anti-loose structure everywhere at the pipe support plate in the top, in a row spacing screw rod, any spacing screw flight lost efficacy, and can cause the global failure of permutation spacing screw rod.And due to the special construction of bundle of steam generator, can't again tighten after the spacing screw failure.
Summary of the invention
The purpose of this utility model is to provide a kind of PWR nuclear power plant steam generator spacing screw rod anti-loose structure.
The technical solution of the utility model is as follows:
a kind of PWR nuclear power plant steam generator spacing screw rod anti-loose structure, it comprises pipe positioning plate and the more piece spacing screw rod that is arranged on the pipe positioning plate, be processed with curve bath on described spacing screw rod, be processed with the rectangle counterbore on described pipe positioning plate, the two joint spacing screw rods that are connected are arranged on the pipe positioning plate by the rectangle counterbore, be provided with lock washer in described rectangle counterbore, this lock washer is sleeved on outside the spacing screw rod, and cover curve bath, lower spacing screw rod is fixedly connected with upper spacing screw rod by screw thread, described lock washer comprises thin cylinder and the rectangular base of energy extrusion-deformation.
In above-mentioned a kind of PWR nuclear power plant steam generator spacing screw rod anti-loose structure, be provided with end nut outside the upper end of the spacing screw rod of described the top, described end nut is cylindrical, its outside is provided with curve bath and serrate slot.
Remarkable result of the present utility model is: owing to being processed with curve bath on the spacing screw rod, when making spacing screw rod and pipe support plate install, the lock washer that adopts can be pressed in curve bath, thereby makes the spacing screw rod can not become flexible in the pipe support plate, prevents from getting loose.Its outside of mounting end nut is provided with curve bath and serrate slot on the spacing screw rod of the top, not only can prevent that the spacing screw rod of the top from getting loose, and simultaneously owing to being processed with serrate slot, also is convenient to tightening of end nut.
Description of drawings
Fig. 1 is the position of spacing screw rod in steam generator;
Fig. 2 .1 is certain in-service kilowatt pressurized water reactor nuclear power station steam generator spacing screw-rod structure;
Fig. 2 .2 is Fig. 2 .1 enlarged view;
Fig. 3 .1 is spacing screw rod schematic diagram;
Fig. 3 .2 is the A-A sectional view of Fig. 3 .1;
Fig. 4 .1 is spacing screw rod anti-loose structure schematic diagram of the present invention;
The E-E direction sectional view of Fig. 4 .2 Fig. 4 .1;
Fig. 5 is the lock washer schematic diagram;
Fig. 6 .1 is the end nut schematic diagram;
Fig. 6 .2 is the B-B direction sectional view of Fig. 6 .1;
Fig. 6 .3 is the C-C direction sectional view of Fig. 6 .1;
In figure: 1. pipe support plate; 2. spacing screw rod; 2.1. upper spacing screw rod; 2.2. lower spacing screw rod; 3. rectangle counterbore; 4. lock washer; 4.1. thin cylinder; 4.2. rectangular base; 5. curve bath; 6. end nut; 7. serrate slot.
Embodiment
Below in conjunction with drawings and the specific embodiments, the utility model is described in further detail.
As shown in Fig. 3 .1 and Fig. 3 .2, the upper end of spacing screw rod 2 is processed with outside thread, and the lower end is processed with internal thread, and the upper end external diameter of spacing screw rod 2 is identical with bottom diameter, therefore makes a plurality of spacing screw rods 2 be threaded connection.Be symmetrily processed with curve bath 5 on the outside of the centre of spacing screw rod 2.
As shown in Fig. 4 .1 and Fig. 4 .2, processing rectangle counterbore 3 on pipe support plate 1, the upper spacing screw rod 2.1 and the lower spacing screw rod 2.2 that connect are positioned at rectangle counterbore 3.Lock washer 4 is put in the upper end of rectangle counterbore 3, and the upper end of lower spacing screw rod 2.2 is put in the lower end of rectangle counterbore 3.
As Fig. 4 .2 and shown in Figure 5, lock washer 4 comprises thin cylinder 4.1 and rectangular base 4.2, and rectangular base 4.2 is positioned at the bottom of thin cylinder 4.1.Because the thin cylinder 4.1 of lock washer 4 can push, so it is pressed in the curve bath 5 of spacing screw rod 2, can prevent that the spacing screw rod from getting loose at pipe support plate 1 internal thread.
At the upper end mounting end nut 6 of spacing screw rod 2 topmost, as shown in Fig. 6 .1, Fig. 6 .2 and Fig. 6 .3, end nut 6 is cylindrical, and at the end nut 6 even processing in the outside, lower end curve baths 5, the outside, upper end is processing serrate slot 7 evenly.During assembling, the thin cylinder of lock washer 4 is pressed in curve bath 5.Serrate slot 7 is convenient to tightening of end nut.
The spacing screw rod 2 that anti-loose structure of the present utility model adopts more piece to be threaded couples together, the rectangle counterbore 3 of processing on pipe support plate 1 is used for installing spacing screw rod 2, adopt rectangle counterbore 3 interior, the outer installation lock washers 4 of spacing screw rod 2, and the position of lock washer 4 correspondences is the curve baths 5 in spacing screw rod 2 outsides, therefore be out of shape because compression produces when lock washer 4 and be pressed in curve bath 5, make lock washer 5 chucking spacing screw rods 2, prevent that spacing screw rod 2 from getting loose in pipe support plate 1.
Same principle, at spacing screw rod 2 topmost, because the upper end does not have curve bath, therefore must take measures to prevent getting loose of spacing screw rod 2 upper ends, thus outside the upper end of the top one joint spacing screw rod 2 by screw thread mounting end nut 6, this end nut 6 outsides also are processed with curve bath 5, also be processed with simultaneously serrate slot 7, not only can prevent that the spacing screw rod 2 of the top from getting loose by end nut 6, simultaneously owing to being processed with serrate slot 7, also be convenient to tightening of end nut 6.
Claims (2)
1. PWR nuclear power plant steam generator spacing screw rod anti-loose structure, it comprises pipe positioning plate (1) and is arranged on more piece spacing screw rod (2) on pipe positioning plate (1), it is characterized in that: be processed with curve bath (5) on described spacing screw rod (1), be processed with rectangle counterbore (3) on described pipe positioning plate (1), the two joint spacing screw rods (2) that are connected are arranged on pipe positioning plate (1) by rectangle counterbore (3), be provided with lock washer (4) in described rectangle counterbore (3), this lock washer (4) is sleeved on outside spacing screw rod (2.1), and cover curve bath (5), lower spacing screw rod (2.2) is fixedly connected with upper spacing screw rod 2.1 by screw thread, described lock washer (4) comprises thin cylinder (4.1) and the rectangular base (4.2) of energy extrusion-deformation.
2. a kind of PWR nuclear power plant steam generator spacing screw rod anti-loose structure as claimed in claim 1, it is characterized in that: be provided with end nut (6) outside the upper end of the spacing screw rod (2) of described the top, described end nut (6) is cylindrical, and its outside is provided with curve bath (5) and serrate slot (7).
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
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CN 201320203348 CN203272395U (en) | 2013-04-22 | 2013-04-22 | Fixed-pitch threaded rod looseness preventing structure of pressurized water reactor nuclear power plant vapor generator |
Applications Claiming Priority (1)
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CN 201320203348 CN203272395U (en) | 2013-04-22 | 2013-04-22 | Fixed-pitch threaded rod looseness preventing structure of pressurized water reactor nuclear power plant vapor generator |
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CN203272395U true CN203272395U (en) | 2013-11-06 |
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CN 201320203348 Withdrawn - After Issue CN203272395U (en) | 2013-04-22 | 2013-04-22 | Fixed-pitch threaded rod looseness preventing structure of pressurized water reactor nuclear power plant vapor generator |
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Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104110431A (en) * | 2013-04-22 | 2014-10-22 | 中国核动力研究设计院 | Anti-loose structure for distance screws of steam generator of nuclear power plant with pressurized water reactors |
CN111140830A (en) * | 2019-11-26 | 2020-05-12 | 深圳中广核工程设计有限公司 | Vertical steam generator of pressurized water reactor nuclear power station and loose part trapping device thereof |
-
2013
- 2013-04-22 CN CN 201320203348 patent/CN203272395U/en not_active Withdrawn - After Issue
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104110431A (en) * | 2013-04-22 | 2014-10-22 | 中国核动力研究设计院 | Anti-loose structure for distance screws of steam generator of nuclear power plant with pressurized water reactors |
CN104110431B (en) * | 2013-04-22 | 2016-05-18 | 中国核动力研究设计院 | PWR nuclear power plant steam generator spacing screw rod anti-loose structure |
CN111140830A (en) * | 2019-11-26 | 2020-05-12 | 深圳中广核工程设计有限公司 | Vertical steam generator of pressurized water reactor nuclear power station and loose part trapping device thereof |
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Legal Events
Date | Code | Title | Description |
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C14 | Grant of patent or utility model | ||
GR01 | Patent grant | ||
AV01 | Patent right actively abandoned |
Granted publication date: 20131106 Effective date of abandoning: 20160518 |
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C25 | Abandonment of patent right or utility model to avoid double patenting |