阅读说明：本技术 一种主管道和反应堆冷却剂环路 (Main pipeline and reactor coolant loop ) 是由 于坚 于 2020-04-14 设计创作，主要内容包括：本发明属于压水堆核电站设计技术,具体涉及一种主管道和反应堆冷却剂环路。主管道用于连接反应堆压力容器、蒸汽发生器和主泵,热段主管道连接在反应堆压力容器冷却剂出口与蒸汽发生器之间,冷段主管道与主泵泵壳为一体化结构,带有主泵泵壳的冷段主管道连接在蒸汽发生器与反应堆压力容器冷却剂入口之间。本发明采用一种带有主泵泵壳结构的主管道和由该主管道参与组成的反应堆冷却剂环路,与原有技术相比,可减少主管道安装焊接工作量,有利于降低成本,缩短工期,提高核电站建造和运营的安全性和经济性。(The invention belongs to the pressurized water reactor nuclear power plant design technology, and particularly relates to a main pipeline and a reactor coolant loop. The main pipeline is used for connecting a reactor pressure vessel, a steam generator and a main pump, the hot section main pipeline is connected between a coolant outlet of the reactor pressure vessel and the steam generator, the cold section main pipeline and a pump shell of the main pump are of an integrated structure, and the cold section main pipeline with the pump shell of the main pump is connected between a coolant inlet of the steam generator and the reactor pressure vessel. Compared with the prior art, the invention adopts the main pipeline with the main pump shell structure and the reactor coolant loop formed by the main pipeline, thereby reducing the workload of installation and welding of the main pipeline, being beneficial to reducing the cost, shortening the construction period and improving the safety and the economical efficiency of construction and operation of the nuclear power station.)

1. A main pipe and reactor coolant loop, the main pipe being for connecting a reactor pressure vessel, a steam generator and a main pump, characterized in that: the hot section main pipeline is connected between a reactor pressure vessel coolant outlet and a steam generator, the cold section main pipeline and a main pump casing are of an integrated structure, and the cold section main pipeline with the main pump casing is connected between the steam generator and a reactor pressure vessel coolant inlet.

2. The main conduit and reactor coolant loop of claim 1, wherein: the bottom head of the steam generator is provided with two elbow pipe nozzles, the first elbow pipe nozzle is connected with the hot section main pipeline, and the second elbow pipe nozzle is connected with the cold section main pipeline.

3. The main conduit and reactor coolant loop of claim 2, wherein: the pipe end of the cold section main pipeline with the main pump shell structure is provided with an adjusting section, and when the main pipeline of the whole loop is installed and welded, the hot section main pipeline and the cold section main pipeline are welded by 4 welding seams in total, and the welding seams are only horizontally and fixedly butted with one welding position.

4. The main conduit and reactor coolant loop of claim 2, wherein: and a transition section main pipeline is connected between a second elbow pipe nozzle of the bottom head of the steam generator and the integrated structure of the main pump shell and the cold section main pipeline.

5. The main conduit and reactor coolant loop of claim 4, wherein: the changeover portion trunk line includes two sections L-shaped pipelines, and when the trunk line installation welding of whole loop, including hot section trunk line both ends, cold section trunk line one end, changeover portion trunk line both ends and middle 6 welding seams altogether, the welding seam includes two kinds of welding position of pipeline horizontal fixed butt joint and pipeline vertical fixation butt joint.

6. The main conduit and reactor coolant loop of any one of claims 1-5, wherein: and the pump shell of the main pump is connected with a main pump motor through a pump shell flange.

7. The main conduit and reactor coolant loop of claim 1, wherein: the cold section main pipeline and the main pump casing can be of an integral forging structure or integral 3D printing additive manufacturing, and can also be of a welding combined structure.

Technical Field

The invention belongs to the pressurized water reactor nuclear power plant design technology, and particularly relates to a main pipeline and a reactor coolant loop.

Background

At present, the design of a reactor coolant loop of a domestic pressurized water reactor nuclear power station is mainly shown in figure 1, which is an M310 reactor type 'hot section-transition section-cold section' mode and is formed by combining a reactor pressure vessel 6, a steam generator 7, a main pump 4, a hot section main pipe 1a, a transition section main pipe 1c and a cold section main pipe 1 b. The welding method has the defects that the number of installation welding lines of the main pipeline is relatively large, 2 installation welding lines are respectively arranged in a hot section and a cold section in one loop, 4 installation welding lines are arranged in a transition section, 8 welding lines are arranged in total, 24 welding lines are arranged in total in three loops of a million kilowatt-level unit, 3 welding positions including 2G (vertical fixed butt joint of the pipeline), 5G (horizontal fixed butt joint of the pipeline) and 6G (inclined 45-degree fixed butt joint of the pipeline) are adopted, so that the welding preparation of the main pipeline, the evaluation of the welding process, the welding, the nondestructive inspection, the identification and the like are large in workload, and the installation and welding.

Disclosure of Invention

The invention aims to overcome the defects of the prior art and provide a main pipeline and a reactor coolant loop which can reduce the number of welding seams and improve the safety and the economy of a nuclear power station.

The technical scheme of the invention is as follows: the utility model provides a trunk line and reactor coolant loop, trunk line are used for connecting reactor pressure vessel, steam generator and main pump, and wherein, the hot section trunk line is connected between reactor pressure vessel coolant outlet and steam generator, and cold section trunk line and main pump case structure as an organic whole, the cold section trunk line that has the main pump case is connected between steam generator and reactor pressure vessel coolant entry.

Further, the main pipe and the reactor coolant loop as described above, wherein the bottom head of the steam generator is provided with two elbow nozzles, the first elbow nozzle is connected to the hot section main pipe, and the second elbow nozzle is connected to the cold section main pipe.

Furthermore, the main pipeline and the reactor coolant loop as described above, wherein the pipe end of the cold main pipeline with the main pump casing structure is provided with the adjusting section, when the main pipeline of the whole loop is installed and welded, the welding line comprises 4 welding lines at both ends of the hot main pipeline and both ends of the cold main pipeline, and the welding line only has one welding position for horizontally and fixedly butting the pipelines.

Further, the main pipe and the reactor coolant loop as described above, wherein a transition section main pipe is connected between the second elbow nozzle of the bottom head of the steam generator and the integrated structure of the main pump casing and the cold section main pipe.

Still further, trunk line and reactor coolant loop as above, wherein, the changeover portion trunk line includes two sections L-shaped pipeline, when the trunk line installation welding of whole loop, including hot section trunk line both ends, cold section trunk line one end, changeover portion trunk line both ends and middle 6 welding seams altogether, the welding seam includes two kinds of welding position of pipeline horizontal fixation butt joint and pipeline vertical fixation butt joint.

Further, the main pipe and the reactor coolant loop as described above, wherein the main pump housing is connected to the main pump motor by a pump housing flange.

Further, the main pipeline and the reactor coolant loop as described above, wherein the cold-section main pipeline and the main pump casing may be of an integral forged structure or an integral 3D printing additive manufacturing, or may be of a welded composite structure.

The invention has the following beneficial effects: after the main pipeline, the steam generator bottom head and the reactor coolant loop are adopted, compared with the original M310 type technology, due to the adoption of the main pump shell-cold section main pipeline integrated structure, the number of the main pipeline installation welding lines in one loop is reduced from 8 to 4 or 6, the number of the three loop main pipeline installation welding lines is reduced from 24 to 12 or 18, the original three welding positions of 2G, 5G and 6G are reduced to 5G and one welding position or two welding positions of 2G and 5G, the welding lines needing in-service inspection are also reduced, the construction workload is correspondingly greatly reduced, the cost is favorably reduced, the construction period is shortened, and the safety and the economical efficiency of the construction and the operation of a nuclear power station are improved.

Drawings

FIG. 1 is a schematic view of a coolant loop for a reactor of type M310;

FIG. 2 is a schematic view of an integrated structure of a main pump casing and a cold-section main pipe according to a first embodiment of the present invention;

FIG. 2a is a schematic view of an integrated structure of a main pump casing-cold section main pipe of a second embodiment of the present invention;

FIG. 3 is a schematic view of a main pump-pump housing-cold leg main pipe of the first embodiment of the present invention;

FIG. 4 is a schematic top view of the pump casing-cold section main pipe integrated structure of the main pump according to the first embodiment of the present invention;

FIG. 4a is a schematic top view of a second embodiment of the main pump casing-cold section main pipe integrated structure of the present invention;

FIG. 5 is a schematic side-view expanded view of an integrated structure of a main pump casing-cold section main pipe of the first embodiment of the present invention;

FIG. 5a is a schematic side-view expanded view of a second embodiment of the main pump casing-cold section main pipe integrated structure of the present invention;

FIG. 5b is a schematic diagram of the pipe end adjustment section of the main pipe in the cold section according to the first embodiment of the present invention;

FIG. 6 is a schematic side-view exploded view of a first embodiment of a steam generator bottom head with elbow nozzles of the present invention;

FIG. 6a is a schematic side-view exploded view of a bottom head of a steam generator with elbow nozzles according to a second embodiment of the present invention;

FIG. 7 is a schematic plan view of a reactor coolant loop according to a first embodiment of the present invention;

FIG. 7a is a schematic plan view of a reactor coolant loop according to a second embodiment of the present invention;

FIG. 8 is a schematic side-view expanded view of a reactor coolant loop according to a first embodiment of the present invention;

fig. 8a is a schematic side-view expanded view of a reactor coolant loop according to a second embodiment of the present invention.

In the figure: 1-a main pipeline; 1 a-a hot section main pipeline; 1 b-a cold section main pipeline; 1b 1-transition main pipe; 1b 2-transition main pipe; 2-main pump casing; 3-main pump casing flange; 4-main pump motor; 5 a-installing welding seams of the reactor pressure vessel and the hot section main pipeline; 5 b-installing a welding seam between the main pipeline of the hot section and the first elbow pipe nozzle; 5 c-the second elbow nozzle in the first embodiment is welded with the cold-section main pipeline 1 b; 5c 1-second elbow nozzle in the second embodiment mounting weld with main transition duct 1b 1; 5c 2-main transition segment pipe 1b1 and main transition segment pipe 1b2 in the second embodiment; 5c 3-mounting welding seams of the transition section main pipe 1b2 and the main pump casing 2 in the second embodiment; 5d, installing a welding line between the main pipeline 1b of the cold section and the reactor pressure vessel; 6-reactor pressure vessel; 7-a steam generator; 8 a-a first elbow nozzle; 8 b-second elbow nozzle.

Detailed Description

Embodiments of a main conduit and reactor coolant loop according to the present invention will now be described with reference to the accompanying drawings.