CN113871036A - Reactor coolant loop and installation method thereof - Google Patents

Reactor coolant loop and installation method thereof Download PDF

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Publication number
CN113871036A
CN113871036A CN202110947637.1A CN202110947637A CN113871036A CN 113871036 A CN113871036 A CN 113871036A CN 202110947637 A CN202110947637 A CN 202110947637A CN 113871036 A CN113871036 A CN 113871036A
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main
section
steam generator
pressure vessel
pipe
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CN113871036B (en
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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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    • 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

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  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention belongs to the design technology of a pressurized water reactor nuclear power station, and particularly relates to a reactor coolant loop and an installation method thereof. Compared with the prior art, the reactor pressure vessel with the coolant outlet nozzle plane, the coolant inlet nozzle plane and the axis of the transition section main pipeline parallel to each other is adopted, the horizontal plane projection of the reactor coolant loop is approximately in an inverted U shape, the installation can be simplified, all parts can freely contract when the reactor coolant loop is installed and welded, the loop structure has small restraint degree, and the welding stress can be reduced, so that the construction workload is reduced, the cost is 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.

Description

Reactor coolant loop and installation method thereof
Technical Field
The invention belongs to the design technology of a pressurized water reactor nuclear power station, 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 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, a steam generator, a main pump, a hot section main pipe, a transition section main pipe and a cold section main pipe. 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 period is long.
The Chinese patent application 202010289762.3 provides a reactor coolant loop capable of reducing the number of welding seams and improving the safety and economy of a nuclear power station, the effect of the technical scheme of the embodiment is better, the number of the installation welding seams of three loops of a million kilowatt-level unit can be reduced from 24 to 12, and if the reactor coolant loop of the million kilowatt-level unit adopts the scheme of the second loop of a steam generator with increased capacity, the total number of the installation welding seams of the loops can be further reduced to 8. But the defects are that the requirement on the manufacturing and mounting precision of the main equipment is strict, and the construction difficulty is higher; secondly, the closed loop installation welding line of the reactor coolant loop has large restraint degree and high welding stress, and special temporary support of the steam generator is possibly needed for the welding line (the device is provided with a foreign company patent), so that the construction is complicated and the cost is increased.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provides a reactor coolant loop and an installation method thereof, wherein the reactor coolant loop can reduce the restraint degree of a closed-loop installation welding line of the reactor coolant loop, reduce the welding stress of closed-loop installation, simplify the installation process and improve the safety and the economical efficiency of a nuclear power station.
The technical scheme of the invention is as follows: the utility model provides a reactor coolant loop, connect reactor pressure vessel through the trunk line, steam generator and main pump, hot section trunk line is connected between reactor pressure vessel coolant outlet and steam generator, cold section trunk line and changeover portion trunk line and main pump case structure as an organic whole, changeover portion trunk line and cold section trunk line that have the main pump case are connected between steam generator and reactor pressure vessel coolant entry, wherein, reactor pressure vessel coolant outlet nozzle plane and reactor pressure vessel coolant inlet nozzle plane are parallel with changeover portion trunk line axis.
Further, the reactor coolant loop as described above, wherein the bottom head of the steam generator is provided with an inlet nozzle and an outlet nozzle, the inlet nozzle is connected to the hot section main pipe, and the outlet nozzle is connected to the transition section main pipe.
Further, as mentioned above, in the reactor coolant loop, when the main pipeline of the whole loop is installed and welded, only one welding position is horizontally and fixedly butted with 4 welding seams at two ends of the hot section main pipeline and at ends of the cold section main pipeline and the transition section main pipeline.
Furthermore, two sides of each welding seam are respectively provided with a straight pipe section.
Further, a reactor coolant loop as described above, wherein the transition section main pipe end with the main pump housing and the cold section main pipe end are provided with adjustment sections. Or the inlet pipe nozzle pipe end and the outlet pipe nozzle pipe end on the bottom head of the steam generator are provided with adjusting sections, and the plane of the inlet pipe nozzle on the bottom head of the steam generator is vertical to the plane of the outlet pipe nozzle.
A method for installing a reactor coolant loop adopts a transition section main pipeline and a cold section main pipeline which are provided with adjusting sections at pipe ends and provided with main pump shells, and comprises the following steps:
(1) a transition section main pipe and a cold section main pipe with a main pump shell, a reactor pressure vessel, a hot section main pipe and a steam generator are respectively introduced into mounting positions to be in place;
(2) installing and welding a welding seam between an inlet nozzle of the steam generator and the hot section main pipeline;
(3) the hot section main pipeline and the coolant outlet nozzle of the reactor pressure vessel are assembled; measuring a steam generator outlet nozzle and a reactor pressure vessel coolant inlet nozzle;
(4) measuring and processing pipe end adjusting sections of a transition section main pipeline and a cold section main pipeline with a main pump shell;
(5) the steam generator outlet nozzle, the transition section main pipe and the cold section main pipe with the main pump shell and the reactor pressure vessel coolant inlet nozzle are assembled and installed;
(6) welding a welding seam between an outlet nozzle of the steam generator and a main pipeline of the transition section;
(7) after a welding seam between an outlet nozzle of the steam generator and a main pipeline of the transition section is welded and contracted, the main pipeline of the cold section is aligned and assembled with a coolant inlet nozzle of a reactor pressure vessel;
(8) and simultaneously welding a welding seam of the cold-section main pipeline and the coolant inlet nozzle of the reactor pressure vessel and a welding seam of the hot-section main pipeline and the coolant outlet nozzle of the reactor pressure vessel to finish the installation and welding of a reactor coolant loop.
Further, according to the installation method, in the step (4), the pipe end adjusting sections of the transition section main pipe and the cold section main pipe with the main pump shell are measured and processed by taking the reactor pressure vessel coolant inlet nozzle and the steam generator outlet nozzle as reference and considering the shrinkage of the welding seam, so that the plane of the reactor pressure vessel coolant outlet nozzle and the plane of the reactor pressure vessel coolant inlet nozzle are ensured to be parallel to the axis of the transition section main pipe after installation.
Further, in the installation method as described above, in the step (5), the pipe end of the main pipe of the cold leg after installation is staggered with the coolant inlet nozzle of the reactor pressure vessel by a weld contraction amount.
Another method for installing a reactor coolant loop adopts a steam generator that an inlet nozzle pipe end and an outlet nozzle pipe end on a bottom head are provided with adjusting sections, and the plane of the inlet nozzle is vertical to the plane of the outlet nozzle, and comprises the following steps:
1) a transition section main pipeline with a main pump shell, a cold section main pipeline, a hot section main pipeline and a reactor pressure vessel are respectively introduced into the installation positions to be in place;
2) the cold section main pipeline and a reactor pressure vessel coolant inlet nozzle assembly are installed; the hot section main pipeline and the coolant outlet nozzle of the reactor pressure vessel are assembled; measuring the pipe ends of the main pipeline of the transition section and the welded pipe ends of the main pipeline of the hot section and the steam generator;
3) measuring and processing pipe end adjusting sections of an inlet pipe nozzle and an outlet pipe nozzle on a bottom seal head of the steam generator;
4) introducing a steam generator into the installation position;
5) assembling and installing a steam generator inlet nozzle and a hot section main pipe end, a steam generator outlet nozzle and a transition section main pipe end;
6) welding a welding seam between an inlet nozzle of the steam generator and the hot section main pipeline;
7) after welding seams of an inlet nozzle of the steam generator and the hot section main pipeline are welded and shrunk, aligning and assembling the pipe end of the transition section main pipeline and the outlet nozzle of the steam generator;
8) welding a welding seam between an outlet nozzle of the steam generator and a main pipeline of the transition section;
9) after a welding seam between an outlet nozzle of the steam generator and a main pipeline of the transition section is welded and contracted, the main pipeline of the cold section is aligned and assembled with a coolant inlet nozzle of a reactor pressure vessel;
10) and simultaneously welding a welding seam of the cold-section main pipeline and the coolant inlet nozzle of the reactor pressure vessel and a welding seam of the hot-section main pipeline and the coolant outlet nozzle of the reactor pressure vessel to finish the installation and welding of a reactor coolant loop.
Further, in the installation method, in the step 2), the pipe end of the main pipe of the cold section after installation and the coolant inlet nozzle of the reactor pressure vessel are staggered by a section of weld shrinkage, so that the plane of the coolant outlet nozzle of the reactor pressure vessel and the plane of the coolant inlet nozzle of the reactor pressure vessel after installation are parallel to the axis of the main pipe of the transition section.
Further, in the installation method, in step 3), the pipe end adjusting sections of the inlet pipe nozzle and the outlet pipe nozzle on the bottom head of the steam generator are measured and processed by taking the pipe end of the main pipe in the hot section and the pipe end of the main pipe in the transition section as reference and considering the shrinkage of the welding seam between the inlet pipe nozzle and the main pipe in the hot section of the steam generator.
Further, in the step 5), the outlet nozzle of the steam generator is staggered with the pipe end of the main pipeline of the transition section by a section of welding seam shrinkage after installation.
The invention has the following beneficial effects: after the reactor coolant loop is adopted, compared with the prior art, the reactor pressure vessel with the outlet nozzle plane and the inlet nozzle plane parallel to the axis of the main pipeline of the transition section is adopted, the horizontal plane projection of the reactor coolant loop is approximate to an inverted U shape, the installation can be simplified, the structure restraint degree is small when the loop is installed in a closed loop mode, all parts can freely contract when the reactor coolant loop is installed and welded, the welding stress can be reduced, the construction workload is reduced, the cost is 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 loop diagram of a coolant loop for a M310 reactor;
FIG. 2 is a schematic view of an integrated structure of a cold section-main pump casing-transition section main pipeline of the invention;
FIG. 3 is a schematic view of a steam generator with two elbow nozzles in the bottom head of the present invention;
FIG. 4 is a schematic view of a reactor pressure vessel of the present invention with the loop outlet nozzle plane and inlet nozzle plane parallel;
FIG. 5 is a schematic view of a hot leg main pipe of the present invention;
fig. 6 is a schematic diagram of a reactor coolant loop according to the present invention.
In the figure: 1-a reactor pressure vessel; 2-welding the cold section main pipeline with an inlet nozzle of a reactor pressure vessel; 2 a-reactor pressure vessel inlet nozzle; 3-a cold section main pipeline; 4-main pump casing; 5-transition section main pipeline; 6-welding the outlet nozzle of the steam generator with the main pipeline of the transition section; 6 a-steam generator outlet nozzle; 7-a steam generator; 8-welding an inlet nozzle of the steam generator with a main hot section pipeline; 8 a-steam generator inlet nozzle; 9-hot section main pipeline; 10-welding a hot section main pipeline and an outlet nozzle of a reactor pressure vessel; 10 a-reactor pressure vessel outlet nozzle.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
Example one
The embodiment of the invention provides a main pipe and a reactor coolant loop, as shown in fig. 6, a cold-section main pipe 3, a transition-section main pipe 5 and a hot-section main pipe 9 are used for connecting a reactor pressure vessel 1, a steam generator 7 and a main pump 4. Wherein a hot leg main pipe 9 is connected between the steam generator 7 and the reactor pressure vessel 1. As shown in fig. 3, the bottom head of the steam generator 7 is provided with two elbow nozzles (inlet nozzle 8a, outlet nozzle 6 a); the bottom seal head of the steam generator 7 can be provided with a single-leg support to improve the accessibility of installation welding and nondestructive testing of the main pipeline; as shown in fig. 4, the reactor pressure vessel 1 is provided with an inlet nozzle 2a and an outlet nozzle 10 a. In fig. 6, the hot leg main conduit 9 is connected between an inlet nozzle 8a of the steam generator 7 and an outlet nozzle 10a of the reactor pressure vessel 1 via a weld 8 and a weld 10.
As shown in fig. 2, the cold-section main pipe 3 and the transition-section main pipe 5 are integrated with the main pump casing 4; in fig. 6, the main transition duct 5 with the main pump housing 4 and the main cold leg duct 3 are connected between the steam generator 7 outlet nozzle 6a and the reactor pressure vessel 1 inlet nozzle 2a via the weld 6 and weld 2.
In the reactor coolant loop of the present embodiment, as shown in fig. 2, 3, and 4, the pipe end of the cold leg main pipe 3 connected to the reactor pressure vessel inlet nozzle 2a and the pipe end of the transition leg main pipe 5 connected to the steam generator outlet nozzle 6a, which have the main pump casing structure, are provided with adjustment sections for compensating for the manufacturing and installation deviation of the main equipment to ensure the alignment and pairing of the main pipe grooves, and the adjustment sections are measured and processed by taking the reactor pressure vessel inlet nozzle 2a and the steam generator outlet nozzle 6a as references and considering the shrinkage of the weld 6. As shown in fig. 6, when the main pipes of the whole loop are installed and welded, the main pipes include four welding lines in total, namely welding lines 8 and 10 at two ends of the hot-section main pipe 9 and welding lines 2 and 6 at two ends of the transition-section main pipe 5 and the cold-section main pipe 3, and the welding positions of the four welding lines are all horizontally and fixedly butted with each other. An independent leg support can be arranged below the pump shell of the main pump to improve the accessibility of installation welding and nondestructive testing of the main pipeline.
As shown in fig. 4 and 6, the plane of the coolant outlet nozzle 10a of the reactor pressure vessel 1 and the plane of the coolant inlet nozzle 2a of the reactor pressure vessel are parallel to the axis of the main pipeline 5 of the transition section, so that the horizontal projection of the loop of the reactor coolant 10a to 2a is approximately in an inverted U shape. As shown in fig. 2, 4, 5 and 6, two sides of the welding seam 2, two sides of the welding seam 6, two sides of the welding seam 8 and two sides of the welding seam 10 are respectively provided with a straight section to facilitate the welding and nondestructive testing operation.
The installation method of the reactor coolant loop as described above is as follows:
(1) a transition section main pipe 5 with a main pump shell 4 structure, a cold section main pipe 3, a reactor pressure vessel 1, a hot section main pipe 9 and a steam generator 7 are respectively introduced into the installation positions to be in place;
(2) installing and welding a welding seam 8 for welding an inlet nozzle 8a of the steam generator 7 and a main hot section pipeline 9;
(3) the hot section main pipeline 9 and an outlet nozzle 10a of the reactor pressure vessel 1 are assembled and fixed; measuring the steam generator 7 outlet nozzle 6a and the reactor pressure vessel 1 coolant inlet nozzle 2 a;
(4) measuring and processing the adjusting sections of the cold-section main pipe 3 and the transition-section main pipe 5 with the main pump casing 4 by taking the inlet pipe mouth 2a of the reactor pressure vessel 1 and the outlet pipe mouth 6a of the steam generator 7 as reference and considering the shrinkage of the welding seam 6;
(5) assembling and installing a steam generator outlet nozzle 6a, a cold-section main pipe 3 with a main pump shell 4, a transition-section main pipe 5 and a reactor pressure vessel inlet nozzle 2a, wherein the welding shrinkage of a section of welding line 6 is staggered between the cold-section main pipe 3 and the reactor pressure vessel inlet nozzle 2a after installation;
(6) welding a welding seam 6 between an outlet nozzle 6a of the steam generator 7 and the transition section main pipeline 5;
(7) an outlet nozzle 6a of the steam generator 7 is welded with a welding seam 6 of the transition section main pipeline 5 and then shrinks along the axial direction of the transition section main pipeline 5, and the cold section main pipeline 3 is aligned and paired with an inlet nozzle 2a of the reactor pressure vessel 1;
(8) and simultaneously welding a welding seam 2 between the cold-section main pipeline 3 and the inlet nozzle of the reactor pressure vessel 1 and a welding seam 10 between the hot-section main pipeline 9 and the outlet nozzle of the reactor pressure vessel 1 to finish the installation and welding of a reactor coolant loop.
Example two
The invention also provides a second specific embodiment of a reactor coolant loop, in the embodiment, the connection relationship among the cold-section main pipeline 3, the transition-section main pipeline 5, the hot-section main pipeline 9, the reactor pressure vessel 1, the steam generator 7 and the main pump 4 is the same as that of the first embodiment, and the cold-section main pipeline 3, the transition-section main pipeline 5 and the main pump shell 4 are of an integrated structure. The difference from the first embodiment is that the inlet pipe nozzle 8a pipe end and the outlet pipe nozzle 6a pipe end on the bottom head of the steam generator 7 are provided with adjusting sections for compensating the manufacturing and installation deviation of main equipment to ensure that the main pipeline bevels are aligned and paired, the plane of the inlet pipe nozzle 8a is vertical to the plane of the outlet pipe nozzle 6a, and the two pipe ends of the main pipeline 9 in the hot section of fig. 5 are parallel to each other.
The installation method of the reactor coolant loop comprises the following steps:
1) a transition section main pipeline 5 with a main pump shell 4, a cold section main pipeline 3, a hot section main pipeline 9 and a reactor pressure vessel 1 are respectively introduced into the installation positions to be in place;
2) the cold section main pipeline 3 and the reactor pressure vessel coolant inlet nozzle 2a are assembled in a pairing mode, the fact that the plane of a reactor pressure vessel coolant outlet nozzle 10a and the plane of a reactor pressure vessel coolant inlet nozzle 2a are parallel to the axis of the transition section main pipeline 5 after installation is guaranteed, and the welding shrinkage of a section of welding line 6 is staggered between the pipe end of the cold section main pipeline 3 and the reactor pressure vessel coolant inlet nozzle 2a after installation; the hot section main pipeline 9 and a reactor pressure vessel coolant outlet nozzle 10a are assembled; measuring the pipe ends of the main pipe 5 of the transition section and the main pipe 9 of the hot section and welding the pipe ends of the steam generator 7;
3) measuring and processing pipe end adjusting sections of an inlet pipe nozzle 8a and an outlet pipe nozzle 6a on a bottom end socket of a steam generator 7 by taking the pipe end of a main hot-section pipeline 9 and the pipe end of a main transition-section pipeline 5 as reference and considering the welding shrinkage of a welding seam 8 between the inlet pipe nozzle 8a of the steam generator and the main hot-section pipeline 9;
4) the steam generator 7 is brought into position at the installation site;
5) assembling and installing an inlet pipe nozzle 8a of a steam generator 7 and a pipe end of a hot section main pipe 9, an outlet pipe nozzle 6a of the steam generator 7 and a pipe end of a transition section main pipe 5, wherein the outlet pipe nozzle 6a of the steam generator and the pipe end of the transition section main pipe 5 are staggered by welding shrinkage of a section of welding seam 8 after installation;
6) welding a welding seam 8 of an inlet nozzle 8a of the steam generator 7 and a main hot section pipeline 9;
7) an inlet nozzle 8a of the steam generator 7 is welded and shrunk with a welding seam 8 of a hot section main pipe 9, and the pipe end of the transition section main pipe 5 is aligned and paired with an outlet nozzle 6a of the steam generator 7;
8) welding an outlet nozzle 6a of the steam generator 7 with a main pipeline welding seam 6 of the transition section;
9) an outlet nozzle 6a of the steam generator 7 is welded and contracted with a welding seam 6 of a transition section main pipeline, and a cold section main pipeline 3 is aligned and paired with a coolant inlet nozzle 2a of the reactor pressure vessel;
10) and simultaneously welding a welding seam 2 of the cold-section main pipeline 3 and a coolant inlet nozzle of the reactor pressure vessel and a welding seam 10 of the hot-section main pipeline 9 and a coolant outlet nozzle of the reactor pressure vessel to finish the installation and welding of a reactor coolant loop.
It will be evident to those skilled in the art that the invention is not limited to the details of the foregoing illustrative embodiments, and that the present invention may be embodied in other specific forms without departing from the spirit or essential attributes thereof. The present embodiments are therefore to be considered in all respects as illustrative and not restrictive, the scope of the invention being indicated by the appended claims rather than by the foregoing description, and all changes which come within the meaning and range of equivalency of the claims are therefore intended to be embraced therein. Any reference sign in a claim should not be construed as limiting the claim concerned.
Furthermore, it should be understood that although the present description refers to embodiments, not every embodiment may contain only a single embodiment, and such description is for clarity only, and those skilled in the art should integrate the description, and the embodiments may be combined as appropriate to form other embodiments understood by those skilled in the art.

Claims (13)

1. The utility model provides a reactor coolant loop, connect reactor pressure vessel through the trunk line, steam generator and main pump, hot section trunk line is connected between reactor pressure vessel coolant outlet and steam generator, cold section trunk line and changeover portion trunk line and main pump case structure as an organic whole, changeover portion trunk line and cold section trunk line that have the main pump case are connected between steam generator and reactor pressure vessel coolant entry, a serial communication port, reactor pressure vessel coolant outlet nozzle plane and reactor pressure vessel coolant inlet nozzle plane are parallel with changeover portion trunk line axis.
2. The reactor coolant loop of claim 1 wherein the bottom head of the steam generator is provided with an inlet nozzle and an outlet nozzle, the inlet nozzle being connected to the hot leg main conduit and the outlet nozzle being connected to the transition leg main conduit.
3. The reactor coolant loop of claim 1 or 2 wherein, during installation welding of the main pipe of the whole loop, only 4 welding seams at the two ends of the main pipe of the hot section and the ends of the main pipe of the cold section and the main pipe of the transition section are horizontally and fixedly butted at one welding position.
4. The reactor coolant loop of claim 3 wherein each of said welds has a straight tube section on each side.
5. The reactor coolant loop of claim 1 or 2 wherein the transition section main pipe end with the main pump housing and the cold section main pipe end are provided with adjustment sections.
6. The reactor coolant loop of claim 2 wherein the inlet nozzle tube end and the outlet nozzle tube end of the steam generator bottom head are provided with adjustment segments, the plane of the inlet nozzle tube of the steam generator bottom head being perpendicular to the plane of the outlet nozzle tube.
7. A method of installing a reactor coolant loop according to claim 5, comprising the steps of:
(1) a transition section main pipe and a cold section main pipe with a main pump shell, a reactor pressure vessel, a hot section main pipe and a steam generator are respectively introduced into mounting positions to be in place;
(2) installing and welding a welding seam between an inlet nozzle of the steam generator and the hot section main pipeline;
(3) the hot section main pipeline and the reactor pressure vessel coolant outlet nozzle are assembled, and a steam generator outlet nozzle and a reactor pressure vessel coolant inlet nozzle are measured;
(4) measuring and processing pipe end adjusting sections of a transition section main pipeline and a cold section main pipeline with a main pump shell;
(5) the steam generator outlet nozzle, the transition section main pipe and the cold section main pipe with the main pump shell and the reactor pressure vessel coolant inlet nozzle are assembled and installed;
(6) welding a welding seam between an outlet nozzle of the steam generator and a main pipeline of the transition section;
(7) welding and shrinking a welding seam between an outlet nozzle of the steam generator and a main pipeline of the transition section, and aligning and pairing the main pipeline of the cold section and a coolant inlet nozzle of the reactor pressure vessel;
(8) and simultaneously welding a welding seam of the cold-section main pipeline and the coolant inlet nozzle of the reactor pressure vessel and a welding seam of the hot-section main pipeline and the coolant outlet nozzle of the reactor pressure vessel to finish the installation and welding of a reactor coolant loop.
8. The method for installing a reactor coolant loop according to claim 7, wherein in the step (4), the pipe end adjustment sections of the main transition-section pipe and the main cold-section pipe with the pump casing of the main pump are measured and processed by taking the coolant inlet nozzle of the reactor pressure vessel and the coolant outlet nozzle of the steam generator as references and taking the shrinkage of the weld into consideration, so as to ensure that the plane of the coolant outlet nozzle of the reactor pressure vessel and the plane of the coolant inlet nozzle of the reactor pressure vessel are parallel to the axis of the main transition-section pipe after installation.
9. The method of installing a reactor coolant loop of claim 8 wherein in step (5) the cold leg main pipe end is offset from the reactor pressure vessel coolant inlet nozzle by a weld contraction amount after installation.
10. A method of installing a reactor coolant loop according to claim 6, comprising the steps of:
1) a transition section main pipeline with a main pump shell, a cold section main pipeline, a hot section main pipeline and a reactor pressure vessel are respectively introduced into the installation positions to be in place;
2) the cold section main pipeline and a reactor pressure vessel coolant inlet nozzle assembly are installed; the hot section main pipeline and the coolant outlet nozzle of the reactor pressure vessel are assembled; measuring the pipe end of a transition section main pipe and the pipe end of a hot section main pipe steam generator side;
3) measuring and processing pipe end adjusting sections of an inlet pipe nozzle and an outlet pipe nozzle on a bottom seal head of the steam generator;
4) introducing a steam generator into the installation position;
5) assembling and installing a steam generator inlet nozzle and a hot section main pipe end, a steam generator outlet nozzle and a transition section main pipe end;
6) welding a welding seam between an inlet nozzle of the steam generator and the hot section main pipeline;
7) welding seams of an inlet nozzle of the steam generator and a hot section main pipe are welded and shrunk, and a pipe end of a transition section main pipe is aligned and paired with an outlet nozzle of the steam generator;
8) welding a welding seam between an outlet nozzle of the steam generator and a main pipeline of the transition section;
9) welding and shrinking a welding seam between an outlet nozzle of the steam generator and a main pipeline of the transition section, and aligning and pairing the main pipeline of the cold section and a coolant inlet nozzle of the reactor pressure vessel;
10) and simultaneously welding a welding seam of the cold-section main pipeline and the coolant inlet nozzle of the reactor pressure vessel and a welding seam of the hot-section main pipeline and the coolant outlet nozzle of the reactor pressure vessel to finish the installation and welding of a reactor coolant loop.
11. The method for installing a reactor coolant loop of claim 10, wherein in step 2), the tube end of the main cold leg after installation is staggered from the coolant inlet nozzle of the reactor pressure vessel by a weld contraction amount to ensure that the plane of the coolant outlet nozzle of the reactor pressure vessel and the plane of the coolant inlet nozzle of the reactor pressure vessel are parallel to the axis of the main transition leg after installation.
12. The method for installing the reactor coolant loop of claim 10, wherein in the step 3), the pipe end adjusting sections of the inlet nozzle and the outlet nozzle of the bottom head of the steam generator are measured and processed by taking the pipe end of the main hot-section pipe and the pipe end of the main transition section pipe as reference and considering the shrinkage of the welding seam between the inlet nozzle and the main hot-section pipe of the steam generator.
13. The method of installing a reactor coolant loop of claim 10 wherein in step 5) the steam generator outlet nozzle is offset from the transition main tube end by a weld contraction after installation.
CN202110947637.1A 2021-08-18 2021-08-18 Reactor coolant loop and installation method thereof Active CN113871036B (en)

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Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3135572A1 (en) * 1981-09-08 1983-03-17 Kraftwerk Union AG, 4330 Mülheim Nuclear reactor, in particular pressurised water reactor having one reactor pressure vessel and a plurality of coolant loops (circuits)
US4579087A (en) * 1983-12-21 1986-04-01 Westinghouse Electric Corp. Corrosion resistant steam generator and method of making same
CN107591213A (en) * 2017-07-31 2018-01-16 清华大学天津高端装备研究院 Integrated pressurized water reactor
CN107785084A (en) * 2017-07-31 2018-03-09 清华大学天津高端装备研究院 A kind of integrated cold containers type reactor of self-pressurization type
CN111599496A (en) * 2020-04-14 2020-08-28 中国核电工程有限公司 Main pipeline and reactor coolant loop

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3135572A1 (en) * 1981-09-08 1983-03-17 Kraftwerk Union AG, 4330 Mülheim Nuclear reactor, in particular pressurised water reactor having one reactor pressure vessel and a plurality of coolant loops (circuits)
US4579087A (en) * 1983-12-21 1986-04-01 Westinghouse Electric Corp. Corrosion resistant steam generator and method of making same
CN107591213A (en) * 2017-07-31 2018-01-16 清华大学天津高端装备研究院 Integrated pressurized water reactor
CN107785084A (en) * 2017-07-31 2018-03-09 清华大学天津高端装备研究院 A kind of integrated cold containers type reactor of self-pressurization type
CN111599496A (en) * 2020-04-14 2020-08-28 中国核电工程有限公司 Main pipeline and reactor coolant loop

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