CN115274149A - Reactor coolant loop and installation method thereof - Google Patents

Reactor coolant loop and installation method thereof Download PDF

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Publication number
CN115274149A
CN115274149A CN202210920566.0A CN202210920566A CN115274149A CN 115274149 A CN115274149 A CN 115274149A CN 202210920566 A CN202210920566 A CN 202210920566A CN 115274149 A CN115274149 A CN 115274149A
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China
Prior art keywords
cold
pipe
hot
nozzle
pressure vessel
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CN202210920566.0A
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Chinese (zh)
Inventor
于坚
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China Nuclear Power Engineering Co Ltd
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China Nuclear Power Engineering Co Ltd
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Priority to CN202210920566.0A priority Critical patent/CN115274149A/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Abstract

The invention provides a reactor coolant loop and a method for installing the same, wherein the method comprises the following steps: the system comprises a reactor pressure vessel, a steam generator with a main pump, a hot-section main pipe and a cold-section main pipe; because of the perpendicular line of hot leg trunk line and reactor pressure vessel butt joint face is parallel with the perpendicular line of cold leg trunk line and reactor pressure vessel butt joint face, the perpendicular line of steam generator and cold leg trunk line butt joint face is perpendicular with the perpendicular line of reactor pressure vessel and cold leg trunk line butt joint face, the loop of reactor pressure vessel coolant export mouthpiece to reactor pressure vessel coolant import mouthpiece is door-shaped structure after improving, the groove group is simple and easy, each part group of loop is to homoenergetic freely shrink when welding to reduced loop structure welding degree of restraint and welding stress, reduced loop installation welding seam quantity and welding position simultaneously, be favorable to reducing cost and improving, improve the security and the economic nature of nuclear power station construction and operation.

Description

Reactor coolant loop and installation method thereof
Technical Field
The invention belongs to the field of pressurized water reactor nuclear power station construction, and particularly relates to a reactor coolant loop and an installation method thereof.
Background
At present, the design of a reactor coolant loop of a domestic pressurized water reactor nuclear power station mainly comprises an M310 type 1 hot section-1 transition section-1 cold section mode and an AP1000 type 1 hot section-2 cold section mode. As shown in fig. 1, the AP1000 type reactor coolant loop structure is more compact because a steam generator is attached with a main pump to omit a transition section, but has the disadvantages that 3 welding grooves need to be butted simultaneously between a bottom head nozzle and a pump shell nozzle and a main pipeline when the steam generator is installed, so that the assembly of the main pipeline installation welding grooves is complicated, difficult and high in risk, and the loop assembly has high welding restraint degree and high welding stress and welding deformation risk; and 1 loop of the welding device has 6 installation welding seams, 2 loops of a million kilowatt-level unit have 12 installation welding seams, and 5GT and 6GT have 2 welding positions, so that the welding preparation of a main pipeline, the evaluation of a welding process, the welding, the nondestructive inspection and other workloads are large, and the installation and welding period is long.
Disclosure of Invention
The invention aims to solve the technical problem of providing a reactor coolant loop which reduces the difficulty of groove assembly, the number of welding seams and welding positions and reduces the welding restraint and the welding stress of loop structure assembly aiming at the defects in the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows:
the present invention provides a reactor coolant loop comprising: the system comprises a reactor pressure vessel, a steam generator with a main pump, a hot-section main pipe and a cold-section main pipe;
the hot section main pipeline is horizontally and fixedly welded between the reactor pressure vessel and the steam generator in a pipe butt joint mode;
the cold section main pipeline is horizontally and fixedly welded between the reactor pressure vessel and the steam generator in a pipe butt joint mode;
the vertical line of the butt joint surface of the hot-section main pipeline and the reactor pressure vessel is parallel to the vertical line of the butt joint surface of the cold-section main pipeline and the reactor pressure vessel;
and the vertical line of the butt joint surface of the cold-section main pipeline and the steam generator is vertical to the vertical line of the butt joint surface of the cold-section main pipeline and the reactor pressure vessel.
Optionally, a bottom head of the steam generator is provided with a hot end pump shell and a cold end pump shell;
a nozzle of the hot end pump shell is connected with a hot section main pipeline, and the lower end of the hot end pump shell is connected with a hot end main pump motor;
a nozzle of the cold end pump shell is connected with a cold section main pipeline, and the lower end of the cold end pump shell is connected with a cold end main pump motor; or the like, or, alternatively,
the bottom head of the steam generator is provided with a hot end elbow and a cold end pump shell;
the nozzle of the hot end elbow is connected with the hot section main pipeline;
the nozzle of the cold end pump shell is connected with the cold section main pipeline, and the lower end of the cold end pump shell is connected with a cold end main pump motor.
Optionally, the cold section main pipeline is an L-shaped pipeline and includes a short section and a long section after continuous bending, the short section pipe end is connected with the nozzle end of the cold end pump housing, and the long section pipe end is connected with the nozzle end of the coolant inlet pipe of the reactor pressure vessel. And the plane of the pump shell end of the cold section main pipeline is vertical to the plane of the reactor pressure vessel end.
Optionally, the cold section main pipeline long section and the hot section main pipeline are straight pipes, and the cold section main pipeline long section is parallel to the hot section main pipeline.
Optionally, the reactor pressure vessel is provided with a coolant inlet nozzle and a coolant outlet nozzle, the nozzle end plane of the coolant inlet nozzle and the nozzle end plane of the coolant outlet nozzle being parallel.
Optionally, one end of the hot section main pipe and both ends of the cold section main pipe are provided with adjusting sections.
Optionally, the nozzle end of the hot end pump shell and the nozzle end of the cold end pump shell of the steam generator are both provided with an adjusting section, or,
and the nozzle end of the hot end elbow of the steam generator and the nozzle end of the cold end pump shell are both provided with adjusting sections.
A method for installing a reactor coolant loop with a cold-section main pipe and an adjusting section comprises the steps of setting welding seams between a steam generator and a hot-section main pipe, between the steam generator and the cold-section main pipe, between a reactor pressure vessel and the hot-section main pipe, and between the reactor pressure vessel and the cold-section main pipe as a first welding seam, a second welding seam, a third welding seam and a fourth welding seam respectively;
the installation method comprises the following steps:
the hot end pump shell nozzle plane or the hot end elbow nozzle plane of the steam generator and the pump shell end plane of the hot section main pipeline are welded in an assembling mode to form a first welding seam;
the end plane of the hot section main pipeline is paired and fixed with the nozzle plane of the reactor pressure vessel coolant outlet nozzle;
measuring and processing adjusting sections at two ends of a cold-section main pipeline by taking a nozzle end of a coolant inlet pipe of the reactor pressure vessel and a nozzle end of a cold-end pump shell pipe of a steam generator as references, and after the pipe ends of the cold-section main pipeline are aligned with a cold-end pump shell pipe nozzle end of a cold-end pump shell of the steam generator, staggering the pipe ends of the cold-section main pipeline and the nozzle end of the coolant inlet pipe of the reactor pressure vessel by the shrinkage of a second welding line;
the pipe end of the cold-section main pipe is welded with the cold-end pump shell pipe nozzle end of the steam generator cold-end pump shell to form a second welding seam, and the second welding seam is welded and contracted to drive the other end of the cold-section main pipe to move and align with the reactor pressure vessel coolant inlet pipe nozzle end;
and the pipe end of the hot section main pipeline and the pipe end of the cold section main pipeline are respectively welded with the coolant outlet pipe mouth end and the coolant inlet pipe mouth end of the reactor pressure vessel to form a third welding line and a fourth welding line, so that the installation of a reactor coolant loop is completed.
The other method for installing the reactor coolant loop with the adjusting section at the nozzle end of the pump shell pipe of the steam generator is that the welding seams between the steam generator and the hot section main pipe, between the steam generator and the cold section main pipe, between the reactor pressure vessel and the hot section main pipe, and between the reactor pressure vessel and the cold section main pipe are respectively a first welding seam, a second welding seam, a third welding seam and a fourth welding seam;
the installation method comprises the following steps:
the hot section main pipeline and the cold section main pipeline are respectively paired and fixed with a coolant outlet pipe mouth end and a coolant inlet pipe mouth end of the reactor pressure vessel, and the pipe end of the cold section main pipeline and the coolant inlet pipe mouth end of the reactor pressure vessel are staggered by the shrinkage of a second welding line;
measuring and processing an adjusting section of a hot end pump shell or a hot end elbow pipe nozzle end of the steam generator and an adjusting section of a cold end pump shell pipe nozzle end of the steam generator by taking a steam generator end of a hot section main pipe and a steam generator end of a cold section main pipe as references, and staggering a shrinkage of a first welding seam between the cold end pump shell pipe nozzle end of the steam generator and the pipe end of the cold section main pipe after the steam generator is assembled with the hot section main pipe;
the main pipeline of the hot section and the nozzle end of a coolant outlet pipe of the reactor pressure vessel are removed from assembly and fixation;
welding the nozzle end of a hot end pump shell or a hot end elbow of the steam generator with the pipe end of a hot section main pipe to form a first welding seam;
after the first welding seam is welded and contracted, the pipe end of the hot section main pipeline is paired and fixed with the pipe end of the coolant outlet pipe nozzle of the reactor pressure vessel, and the pipe end of the cold end pump shell pipe nozzle of the steam generator is aligned and paired with the pipe end of the cold section main pipeline;
the pipe end of the main pipeline at the cold section and the nozzle end of a coolant inlet pipe of the reactor pressure vessel are removed from pairing fixation;
the pipe end of the cold-section main pipeline is welded with the pipe nozzle end of a cold-end pump shell of the steam generator to form a second welding line, and the second welding line is welded and contracted to drive the pipe end of the cold-section main pipeline to move and align with the pipe nozzle end of a coolant inlet pipe of the reactor pressure vessel;
and the pipe end of the hot section main pipeline and the pipe end of the cold section main pipeline are respectively welded with the coolant outlet pipe mouth end and the coolant inlet pipe mouth end of the reactor pressure vessel to form a third welding line and a fourth welding line, so that the installation of a reactor coolant loop is completed.
According to the invention, through redesigning the AP1000 type reactor coolant loop, compared with the original AP1000 type design, as the perpendicular line of the butt joint surface of the hot section main pipeline and the reactor pressure vessel is parallel to the perpendicular line of the butt joint surface of the cold section main pipeline and the reactor pressure vessel, and the perpendicular line of the butt joint surface of the cold section main pipeline and the steam generator is perpendicular to the perpendicular line of the butt joint surface of the cold section main pipeline and the reactor pressure vessel, the loop from the coolant outlet nozzle of the reactor pressure vessel to the coolant inlet nozzle of the reactor pressure vessel is in a door-shaped structure after improvement, the assembly of the grooves is simple and easy, all the parts of the loop can freely contract during welding, and the restraint and the welding stress of the loop structure assembly during welding are reduced. In addition, the structure of the original AP1000 type designed '1 hot section-2 cold section' is simplified into the structure of '1 hot section-1 cold section', the number of main pipeline installation welding lines in one loop is reduced from 6 to 4, the number of two loop main pipeline installation welding lines can be reduced from 12 to 8, the number of two original AP1000 type designed welding positions of 5GT and 6GT is reduced to one welding position of 5GT, accordingly, the construction workload is 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 the nuclear power station are improved.
Drawings
FIG. 1 is a schematic structural diagram of an original AP1000 type reactor coolant loop;
FIG. 2 is a schematic diagram of the reactor coolant loop provided by the present invention;
FIG. 3 is a schematic bottom view of a reactor pressure vessel according to the present invention;
FIG. 4 is a schematic bottom view of a steam generator according to embodiment 1;
FIG. 5 is a schematic side view of a steam generator according to embodiment 1;
FIG. 6 is a schematic bottom view of a steam generator according to embodiment 2;
FIG. 7 is a schematic side view of a steam generator according to embodiment 2;
FIG. 8 is a bottom view of a hot end pump housing or hot end elbow of the present invention;
FIG. 9 is a bottom schematic view of a cold end pump casing according to the present invention.
In the figure: 1-steam generator (only tube plate and bottom head are shown, the rest parts are omitted); 2-hot end main pump motor; 3-hot end pump case; 3 a-hot end elbow; 4-hot end pump shell nozzle plane or hot end elbow nozzle plane; 5-hot section main pipeline pump shell end plane; 6-hot section main pipeline; 7-end plane of reactor pressure vessel of main pipeline of hot section; 8-the plane of the outlet nozzle end of the reactor pressure vessel; 9-reactor pressure vessel outlet nozzle; 10-a reactor pressure vessel; 11-cold-end main pump motor; 12-cold end pump casing nozzle end plane; 13-cold section main pipeline pump shell end plane; 14-cold end pump casing; 15-a cold section main pipeline; 16-cold section main pipeline reactor pressure vessel end plane; 17-plane of inlet nozzle end of reactor pressure vessel; 18-reactor pressure vessel inlet nozzle; 19-cold end pump casing nozzle axis.
Detailed Description
The technical solutions in the present invention will be described clearly and completely with reference to the accompanying drawings, and it is obvious that the described embodiments are some, but not all embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the scope of the present invention.
In the description of the present invention, it should be noted that the indication of orientation or positional relationship, such as "on" or the like, is based on the orientation or positional relationship shown in the drawings, and is only for convenience and simplicity of description, and does not indicate or imply that the device or element referred to must be provided with a specific orientation, constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention.
In the description of the present invention, the terms "first" and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it is to be noted that, unless otherwise explicitly specified or limited, the terms "connected," "disposed," "mounted," "fixed," and the like are to be construed broadly, e.g., as being fixedly or removably connected, or integrally connected; either directly or indirectly through intervening media, or may be interconnected between two elements. The specific meaning of the above terms in the present invention can be understood in specific cases for those skilled in the art.
Example 1:
as shown in fig. 2, the present embodiment provides a reactor coolant loop comprising: the system comprises a reactor pressure vessel 10, a steam generator 1, a hot-section main pipe 6 and a cold-section main pipe 15;
the hot section main pipeline 6 adopts a 5GT welding position, namely, the pipeline is butted and horizontally and fixedly welded between the reactor pressure vessel 10 and the steam generator 1;
the cold section main pipeline 15 adopts a 5GT welding position, namely, the pipeline is horizontally and fixedly welded between the reactor pressure vessel 10 and the steam generator 1 in a butt joint mode;
the perpendicular line of the pipe end surface 7 when the hot-section main pipe 6 is butted with the nozzle end plane 8 of the coolant outlet nozzle 9 of the reactor pressure vessel 10 is parallel to the perpendicular line of the pipe end surface 16 when the cold-section main pipe 15 is butted with the nozzle end plane 17 of the coolant inlet nozzle 18 of the reactor pressure vessel 10;
as shown in fig. 2 and 9, the perpendicular 19 to the cold end pump housing nozzle end plane 12 where the tube end faces 13 of the steam generator 1 and the cold leg main tube 15 are butted is perpendicular to the nozzle end plane 17 of the coolant inlet nozzle 18 where the tube end faces 16 of the reactor pressure vessel 10 and the cold leg main tube 15 are butted.
In the present embodiment, as shown in fig. 2, 4, 5, 8 and 9, the bottom head of the steam generator 1 is provided with a hot end pump casing 3 and a cold end pump casing 14;
a nozzle 4 of the hot end pump shell 3 is connected with a pump shell end 5 of a hot section main pipeline 6, and the lower end of the hot end pump shell 3 is connected with a hot end main pump motor 2;
the nozzle end 12 of the cold end pump shell 14 is connected with the pump shell end 13 of the cold end main pipeline 15, and the lower end of the cold end pump shell 14 is connected with the cold end main pump motor 11.
In this embodiment, as shown in fig. 2, the cold main pipe 15 is an L-shaped pipe, and includes a short section and a long section after being continuously bent, the short section pipe end 13 is connected to the nozzle end 12 of the cold pump casing 14, the long section pipe end 16 is connected to the coolant inlet nozzle end 17 of the reactor pressure vessel 10, and the pump casing end plane 13 of the cold main pipe 15 is perpendicular to the reactor pressure vessel end plane 16.
In this embodiment, as shown in fig. 3, the reactor pressure vessel 10 is provided with a coolant outlet nozzle 9 and a coolant inlet nozzle 18, and the nozzle end plane 8 of the coolant outlet nozzle 9 and the nozzle end plane 17 of the coolant inlet nozzle 18 are parallel.
In the embodiment, as shown in fig. 2, when the distance between the coolant outlet nozzle 9 and the coolant inlet nozzle 18 of the reactor pressure vessel 10 is matched with the distance between the hot-end pump casing nozzle or the hot-end elbow nozzle and the cold-end pump casing nozzle of the steam generator 1, the hot-section main pipe 6 can be a straight pipe, and the long straight section of the cold-section main pipe 15 can be parallel to the hot-section main pipe 6, so that the cost of bending pipes can be saved; conversely, when the distance between the coolant outlet nozzle 9 and the coolant inlet nozzle 18 of the reactor pressure vessel 10 is not matched with the distance between the hot end pump shell nozzle or the hot end elbow nozzle and the cold end pump shell nozzle of the steam generator 1, the long sections of the hot-section main pipe 6 and the cold-section main pipe 15 can adopt bent pipes.
In this embodiment, as shown in fig. 2, one end 5 or 7 of the hot main pipe 6 and both ends 13 and 16 of the cold main pipe 15 are provided with the adjustment sections.
As shown in fig. 2, it is assumed that the welds between the steam generator 1 and the hot main pipe 6 are 4-5, between the steam generator 1 and the cold main pipe 15 are 12-13, between the reactor pressure vessel 10 and the hot main pipe 6 are 7-8, and between the reactor pressure vessel 10 and the cold main pipe 15 are 16-17, which are respectively a first weld, a second weld, a third weld and a fourth weld, and the installation method of the reactor coolant loop of the present embodiment includes:
the hot end pump shell nozzle plane or the hot end elbow nozzle plane 4 of the steam generator 1 and the pump shell end plane 5 of the hot section main pipeline 6 are welded in an assembling mode to form a first welding seam;
an end plane 7 of the hot section main pipeline 6 is paired and fixed with a nozzle plane 8 of a coolant outlet nozzle 9 of a reactor pressure vessel 10;
measuring and processing adjusting sections of two ends 13 and 16 of a cold section main pipeline 15 and making a pipe end 13 of the cold section main pipeline 15 paired with a cold end pump case nozzle end 12 of a steam generator cold end pump case 14 by taking a coolant inlet pipe nozzle end 17 of a reactor pressure vessel 10 and the cold end pump case nozzle end 12 of the steam generator 1 as references, and then staggering shrinkage of a second welding line between the pipe end 16 of the cold section main pipeline 15 and the coolant inlet pipe nozzle end 17 of the reactor pressure vessel 10;
the pipe end 13 of the cold-section main pipe 15 is welded with the cold-end pump shell nozzle end 12 of the cold-end pump shell 14 of the steam generator 1 to form a second welding line, and the second welding line is welded and contracted along the direction 19 to drive the other end 16 of the cold-section main pipe 15 to move and align with the coolant inlet nozzle end 17 of the reactor pressure vessel 10;
and the pipe end 7 of the hot-section main pipeline 6 and the pipe end 16 of the cold-section main pipeline 15 are respectively welded with the coolant outlet pipe mouth end 8 and the coolant inlet pipe mouth end 17 of the reactor pressure vessel 10 to form a third welding line and a fourth welding line, so that the installation of a reactor coolant loop is completed.
Example 2:
this embodiment provides a reactor coolant loop having a configuration substantially the same as that of embodiment 1, except that the nozzle end 4 of the steam generator hot side pump shell 3 and the nozzle end 12 of the cold side pump shell 14 are each provided with a trim section and the hot side main pipe 6 and the cold side main pipe 15 are not provided with a trim section.
As shown in fig. 2, it is assumed that the welds between the steam generator 1 and the hot main pipe 6 are 4-5, between the steam generator 1 and the cold main pipe 15 are 12-13, between the reactor pressure vessel 10 and the hot main pipe 6 are 7-8, and between the reactor pressure vessel 10 and the cold main pipe 15 are 16-17, which are respectively a first weld, a second weld, a third weld and a fourth weld, and the installation method of the reactor coolant loop of the present embodiment includes:
as shown in fig. 2, the hot-section main pipe 6 and the cold-section main pipe 15 are respectively paired and fixed with the coolant outlet nozzle end 8 and the coolant inlet nozzle end 17 of the reactor pressure vessel 10, and the cold-section main pipe end 16 and the coolant inlet nozzle end 17 of the reactor pressure vessel are staggered by the shrinkage of a second welding line;
measuring and processing an adjusting section of a hot end pump shell or a hot end elbow nozzle end 4 of the steam generator 1 and an adjusting section of a cold end pump shell nozzle end 12 of the steam generator 1 by taking a steam generator end 5 of a hot section main pipe 6 and a steam generator end 13 of a cold section main pipe 15 as references, and staggering the shrinkage of a first welding line between the cold end pump shell nozzle end 12 of the steam generator and a pipe end 13 of the cold section main pipe after the steam generator 1 and the hot section main pipe 6 are assembled;
the pipe end 7 of the main pipeline 6 at the hot section is removed from the pairing fixation with the coolant outlet nozzle end 8 of the reactor pressure vessel 10;
a nozzle end 4 of a hot end pump shell or a hot end elbow of the steam generator 1 is welded with a pipe end 5 of a hot end main pipe 6 to form a first welding line;
after the first welding seam is welded and contracted, a pipe end 7 of the hot section main pipe 6 is paired and fixed with a coolant outlet pipe nozzle end 8 of a reactor pressure vessel 10, and a cold end pump shell pipe nozzle end 12 of the steam generator 1 is aligned and paired with a pipe end 13 of a cold section main pipe 15;
the pipe end 16 of the main cold section pipe 15 and the coolant inlet pipe mouth end 17 of the reactor pressure vessel 10 are removed from pairing fixation;
the pipe end 13 of the cold-section main pipeline 15 is welded with the nozzle end 12 of the cold-end pump shell of the steam generator 1 to form a second welding line, and the second welding line is welded and contracted along the direction 19 to drive the pipe end 16 of the cold-section main pipeline 15 to move and align with the coolant inlet nozzle end 17 of the reactor pressure vessel 10;
the pipe end 7 of the hot-section main pipe 6 and the pipe end 16 of the cold-section main pipe 15 are respectively welded with the coolant outlet pipe mouth end 8 and the coolant inlet pipe mouth end 17 of the reactor pressure vessel 10 to form a third welding seam and a fourth welding seam, and the installation of a reactor coolant loop is completed.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.

Claims (8)

1. A reactor coolant loop, comprising: the system comprises a reactor pressure vessel (10), a steam generator (1), a hot section main pipe (6) and a cold section main pipe (15);
the hot section main pipeline (6) is horizontally and fixedly welded between the reactor pressure vessel (10) and the steam generator (1) by adopting pipe butt joint;
the cold section main pipeline (15) is horizontally and fixedly welded between the reactor pressure vessel (10) and the steam generator (1) by adopting pipe butt joint;
the perpendicular line of the end plane (7) butted with the hot section main pipeline (6) and the reactor pressure vessel (10) is parallel to the perpendicular line of the end plane (16) butted with the cold section main pipeline (15) and the reactor pressure vessel (10);
the vertical line of the end plane (12) butted by the steam generator (1) and the cold-section main pipeline (15) is vertical to the vertical line of the end plane (17) butted by the reactor pressure vessel (10) and the cold-section main pipeline (15).
2. The reactor coolant loop of claim 1,
the bottom seal head of the steam generator (1) is provided with a hot end pump shell (3) and a cold end pump shell (14);
a nozzle of the hot end pump shell (3) is connected with a hot section main pipeline (6), and the lower end of the hot end pump shell (3) is connected with a hot end main pump motor (2);
a nozzle of the cold end pump shell (14) is connected with a cold end main pipeline (15), and the lower end of the cold end pump shell (14) is connected with a cold end main pump motor (11); or the like, or, alternatively,
the bottom seal head of the steam generator (1) is provided with a hot end elbow (3 a) and a cold end pump shell (14);
the nozzle of the hot end elbow (3 a) is connected with the hot section main pipeline (6),
the nozzle of cold junction pump case (14) is connected with cold junction trunk line (15), cold junction main pump motor (11) are connected to the lower extreme of cold junction pump case (14).
3. Reactor coolant loop according to claim 1, characterized in that the pump housing end plane (13) of the cold leg main pipe (15) is perpendicular to the reactor pressure vessel end plane (16).
4. Reactor coolant loop according to claim 1, characterized in that the reactor pressure vessel (10) is provided with a coolant inlet nozzle (18) and a coolant outlet nozzle (9), the nozzle end plane (17) of the coolant inlet nozzle (18) and the nozzle end plane (8) of the coolant outlet nozzle (9) being parallel.
5. Reactor coolant loop according to any of claims 1-4, characterized in that one end of the hot leg main pipe (6) and both ends of the cold leg main pipe (15) are provided with adjustment segments.
6. The reactor coolant loop as claimed in any of claims 1 to 4, characterized in that the nozzle end of the hot-end pump housing (3) and the nozzle end of the cold-end pump housing (14) are provided with an adjusting section, or,
the nozzle end of the hot end elbow (3 a) and the nozzle end of the cold end pump shell (14) are both provided with adjusting sections.
7. A method of installing a reactor coolant loop according to claim 5, wherein the weld seams between the steam generator (1) and the main hot leg tube (6), between the steam generator (1) and the main cold leg tube (15), between the reactor pressure vessel (10) and the main hot leg tube (6), and between the reactor pressure vessel (10) and the main cold leg tube (15) are a first weld seam, a second weld seam, a third weld seam, and a fourth weld seam, respectively;
the installation method comprises the following steps:
the hot end pump shell nozzle plane or the hot end elbow nozzle plane (4) of the steam generator (1) and the pump shell end plane (5) of the hot section main pipeline (6) are welded in an assembling mode to form a first welding seam;
an end plane (7) of the hot section main pipeline (6) and a nozzle plane (8) of a reactor pressure vessel coolant outlet nozzle (9) are paired and fixed;
measuring and processing adjusting sections of two ends (13) and (16) of a cold-section main pipeline (15) and pairing the pipe end (13) of the cold-section main pipeline (15) with a cold-end pump shell pipe nozzle end (12) of a steam generator cold-end pump shell (14) by taking a reactor pressure vessel coolant inlet pipe nozzle end (17) and a steam generator cold-end pump shell pipe nozzle end (12) as references, and then staggering the contraction quantity of a second welding line between the pipe end (16) of the cold-section main pipeline (15) and the reactor pressure vessel coolant inlet pipe nozzle end (17);
the pipe end (13) of the cold-section main pipe (15) is welded with the cold-end pump shell nozzle end (12) of the steam generator cold-end pump shell (14) to form a second welding line, and the second welding line is welded and contracted to drive the other end (16) of the cold-section main pipe (15) to move and align with the reactor pressure vessel coolant inlet nozzle end (17);
and the pipe end (7) of the hot section main pipeline (6) and the pipe end (16) of the cold section main pipeline (15) are respectively welded with a coolant outlet pipe mouth end (8) and a coolant inlet pipe mouth end (17) of the reactor pressure vessel to form a third welding line and a fourth welding line, so that the reactor coolant loop installation is completed.
8. A method of installing a reactor coolant loop according to claim 6, wherein the welds between the steam generator (1) and the hot leg main pipe (6), between the steam generator (1) and the cold leg main pipe (15), between the reactor pressure vessel (10) and the hot leg main pipe (6), and between the reactor pressure vessel (10) and the cold leg main pipe (15) are respectively a first weld, a second weld, a third weld, and a fourth weld;
the installation method comprises the following steps:
the hot section main pipeline (6) and the cold section main pipeline (15) are respectively paired and fixed with a coolant outlet pipe mouth end (8) and a coolant inlet pipe mouth end (17) of a reactor pressure vessel (10), and a cold section main pipeline pipe end (16) and the coolant inlet pipe mouth end (17) of the reactor pressure vessel are staggered by the shrinkage of a second welding line;
measuring and processing an adjusting section of a hot end pump shell or a hot end elbow nozzle end (4) of the steam generator (1) and an adjusting section of a cold end pump shell nozzle end (12) of the steam generator (1) by taking a hot section main pipe steam generator end (5) and a cold section main pipe steam generator end (13) as references, and staggering the shrinkage of a first welding line between the cold end pump shell nozzle end (12) of the steam generator and the cold section main pipe end (13) after the steam generator (1) and the hot section main pipe (6) are assembled;
releasing the pairing fixation of the main pipeline (6) of the hot section and the nozzle end (8) of the coolant outlet pipe of the reactor pressure vessel (10);
a nozzle end (4) of a hot end pump shell or a hot end elbow of the steam generator (1) is welded with a pipe end (5) of a hot section main pipe (6) to form a first welding line;
after welding contraction of a first welding line, a pipe end (7) of a hot section main pipeline (6) is paired and fixed with a coolant outlet pipe nozzle end (8) of a reactor pressure vessel (10), and a cold end pump shell pipe nozzle end (12) of a steam generator (1) is aligned and paired with a pipe end (13) of a cold section main pipeline (15);
the pipe end (16) of the main pipeline (15) at the cold section is released from pairing and fixing with the nozzle end (17) of the coolant inlet pipe of the reactor pressure vessel (10);
the pipe end (13) of the cold-section main pipeline (15) is welded with the nozzle end (12) of the cold-end pump shell of the steam generator (1) to form a second welding line, and the second welding line is welded and contracted to drive the pipe end (16) of the cold-section main pipeline (15) to move and align with the nozzle end (17) of the coolant inlet pipe of the reactor pressure vessel (10);
and the pipe end (7) of the hot section main pipeline (6) and the pipe end (16) of the cold section main pipeline (15) are respectively welded with the coolant outlet pipe mouth end (8) and the coolant inlet pipe mouth end (17) of the reactor pressure vessel (10) to form a third welding line and a fourth welding line, and the installation of a reactor coolant loop is completed.
CN202210920566.0A 2022-08-02 2022-08-02 Reactor coolant loop and installation method thereof Pending CN115274149A (en)

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CN202210920566.0A CN115274149A (en) 2022-08-02 2022-08-02 Reactor coolant loop and installation method thereof

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202210920566.0A CN115274149A (en) 2022-08-02 2022-08-02 Reactor coolant loop and installation method thereof

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Publication Number Publication Date
CN115274149A true CN115274149A (en) 2022-11-01

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