WO2014086274A1 - Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant - Google Patents

Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant Download PDF

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Publication number
WO2014086274A1
WO2014086274A1 PCT/CN2013/088417 CN2013088417W WO2014086274A1 WO 2014086274 A1 WO2014086274 A1 WO 2014086274A1 CN 2013088417 W CN2013088417 W CN 2013088417W WO 2014086274 A1 WO2014086274 A1 WO 2014086274A1
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Prior art keywords
section
vertical
nuclear power
surge pipe
voltage stabilizer
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PCT/CN2013/088417
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French (fr)
Chinese (zh)
Inventor
黄伟
隋海明
苏荣福
刘向红
王保平
赖建永
任云
Original Assignee
中国核动力研究设计院
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Application filed by 中国核动力研究设计院 filed Critical 中国核动力研究设计院
Priority to GB1511704.7A priority Critical patent/GB2523706B/en
Publication of WO2014086274A1 publication Critical patent/WO2014086274A1/en
Priority to ZA2015/04856A priority patent/ZA201504856B/en

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • G21C13/032Joints between tubes and vessel walls, e.g. taking into account thermal stresses
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/14Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Definitions

  • the invention belongs to the technical field of nuclear power, and particularly relates to a surge tube of a voltage regulator.
  • the regulator surge tube (hereinafter referred to as the surge tube) has one end connected to the hot section of a loop of the reactor coolant system, and the other end is connected to the lower head of the regulator to deliver the reactor coolant under high temperature, high pressure and strong radioactive conditions, and Other equipment and piping together form the pressure boundary and are one of the most important pipelines in the reactor coolant system.
  • the coolant temperature in the regulator is higher than the temperature in the reactor coolant system, the coolant temperature from the reactor coolant system is low and density during steady state operation of the plant. Large, occupying the lower part of the surge tube; the coolant from the regulator has a high temperature and a low density, occupying the upper part of the surge tube.
  • the above phenomenon is called the thermal stratification phenomenon of the fluctuation tube.
  • the surge tube of PWR nuclear power plant generally adopts a close horizontal arrangement (the elevation angle is only 17 '), so there is a serious thermal stratification on the radial section of the pipeline, and the main body of the corrugated pipe and its key welds (especially fluctuations) The weld at the junction of the tube and the main circuit) causes severe thermal stress effects.
  • the thermal stratification of fluctuating pipes has always been one of the factors that threaten the safety of power plants, and it is also a key issue of concern to the National Nuclear Safety Administration.
  • the cumulative use factor of the fluctuating tube fatigue is already close to the limit.
  • the object of the present invention is to provide a vertically connected wave tube of a pressurized water reactor nuclear power plant voltage regulator, which can effectively relieve the thermal stratification phenomenon to the wave tube and its main pipe nozzle while effectively connecting the voltage regulator to the main circuit.
  • the impact of the office is as follows:
  • a vertically connected wave tube of a pressurized water reactor nuclear power plant voltage regulator comprising a vertical section I, a vertical section II, and an extension between the two, the vertical section I from the main loop pipeline
  • the top is vertically vertical
  • the vertical section II is vertically connected to the bottom of the regulator, and the extension extends upward at an elevation angle of 2 to 5° from the horizontal plane.
  • the extension section is composed of a straight pipe section, a curved section I, a curved section II and a semicircular section; one end of the straight pipe section and the top of the main circuit pipe Vertically connected, the other end of the straight pipe section is connected with the curved section I; the semicircular section is located between the curved section I and the curved section II; one end of the curved section II is vertically connected to the bottom of the regulator, and is bent The other end of the segment II is connected to the semicircular segment.
  • the beneficial effects obtained by the invention are as follows:
  • the vertical section of the design is used to make the wave tube directly out of the main pipe, so that there is no thermal stratification on the weld of the wave tube nozzle on the main pipe;
  • the extension of the middle section of the wave tube The upward extension of the inclination angle of 2 ⁇ 5° effectively alleviates the influence of the thermal stratification effect on the weld of the section.
  • Figure 1 is a side view of a vertically connected surge tube of a pressurized water reactor nuclear power plant regulator
  • Figure 2 is a plan view of Figure 1;
  • the wave tube includes two vertical segments, a vertical segment I 1 and a vertical segment 112, and includes The extension 3 between the two vertical sections 1 and 2, the vertical section I 1 is vertically detached from the top of the main circuit duct, so that there is no thermal delamination on the weld section of the section, thereby ensuring the main The safety and operational life of the pipe running after it is connected.
  • the other vertical section ⁇ 2 is vertically connected to the bottom of the regulator to achieve communication between the main circuit and the regulator.
  • the extension 3 between the vertical sections 1 and 2 and the horizontal plane are optimally selected at an elevation angle of 2.5°, and the curved extension is inclined upward, maintaining the inclination angle, and the slope is sufficiently large to effectively control the influence of the thermal stratification on the extension 3 of the wave tube. .
  • the design of the extension section 3 adopts an optimum form.
  • the extension section 3 is composed of four parts, a straight pipe section 301, a curved section 1303 and a curved section 11304, and a curved section I303.
  • the semicircular section 302 between the curved section II 304 and the four sections constitute a section of the tube which approximates the omega shape.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Structures Of Non-Positive Displacement Pumps (AREA)

Abstract

A vertical connection type surge pipe for a voltage stabilizer of a pressurized water reactor nuclear power plant comprises a vertical section I (1), a vertical section II (2) and an extension section (3) between the two. The vertical section I is vertically connected outside from the top part of a main loop pipeline; the vertical section II is vertically connected upwards with the bottom of a voltage stabilizer; and the extension section extends upwards at an elevation angle of 2-5 degrees with the horizontal plane. By using the vertical sections, the surge pipe is vertically connected outside from a main pipeline, so that the thermal stratification influence on a welding line of a filler neck of the surge pipe on the main pipeline is avoided; and as the extension section in the middle section of the surge pipe extends upwards at the elevation angle of 2-5 degrees, the influence of the thermal stratification effect on the welding line is effectively relieved.

Description

m ^  m ^
压水堆核电站稳压器竖直连接式波动管  PWR nuclear power plant regulator vertical connected wave tube
技术领域  Technical field
本发明属于核电技术领域, 具体涉及一种稳压器波动管。  The invention belongs to the technical field of nuclear power, and particularly relates to a surge tube of a voltage regulator.
 Scene
稳压器波动管 (以下简称波动管) 一端接反应堆冷却剂系统一条环路的 热段, 另一端接稳压器下封头, 在高温、 高压和强放射性条件下输送反应堆 冷却剂, 并与其它设备和管道一起构成压力边界, 是反应堆冷却剂系统中最 重要的管道之一。  The regulator surge tube (hereinafter referred to as the surge tube) has one end connected to the hot section of a loop of the reactor coolant system, and the other end is connected to the lower head of the regulator to deliver the reactor coolant under high temperature, high pressure and strong radioactive conditions, and Other equipment and piping together form the pressure boundary and are one of the most important pipelines in the reactor coolant system.
在压水堆核电厂运行过程中, 由于稳压器中的冷却剂温度比反应堆冷却 剂系统中的温度高, 在电厂稳态运行工况下, 来自反应堆冷却剂系统的冷却 剂温度低、 密度大, 占据波动管的下部; 来自稳压器的冷却剂温度高、 密度 小, 占据波动管的上部。 工程上将上述现象称为波动管热分层现象。 目前压 水堆核电厂波动管普遍采用接近水平的布置方式 (仰角仅 17 ' ), 因此其管 道径向截面上存在严重的热分层现象, 对波动管本体及其关键焊缝 (特别是 波动管与主回路连接处的焊缝) 造成严重热应力影响。 波动管热分层现象一 直是威胁电厂安全的因素之一, 也是国家核安全局关注的重点问题。 在岭澳 一期中, 波动管疲劳累积使用因子已经接近限值。  During operation of a pressurized water reactor nuclear power plant, because the coolant temperature in the regulator is higher than the temperature in the reactor coolant system, the coolant temperature from the reactor coolant system is low and density during steady state operation of the plant. Large, occupying the lower part of the surge tube; the coolant from the regulator has a high temperature and a low density, occupying the upper part of the surge tube. The above phenomenon is called the thermal stratification phenomenon of the fluctuation tube. At present, the surge tube of PWR nuclear power plant generally adopts a close horizontal arrangement (the elevation angle is only 17 '), so there is a serious thermal stratification on the radial section of the pipeline, and the main body of the corrugated pipe and its key welds (especially fluctuations) The weld at the junction of the tube and the main circuit) causes severe thermal stress effects. The thermal stratification of fluctuating pipes has always been one of the factors that threaten the safety of power plants, and it is also a key issue of concern to the National Nuclear Safety Administration. In the Lingao Phase I, the cumulative use factor of the fluctuating tube fatigue is already close to the limit.
发明内容  Summary of the invention
本发明的目的在于提供一种压水堆核电站稳压器竖直连接式波动管, 它 能够稳压器与主回路有效连通的同时, 有效缓解热分层现象对波动管及其主 管道接管嘴处的影响。 实现本发明的技术方案如下: The object of the present invention is to provide a vertically connected wave tube of a pressurized water reactor nuclear power plant voltage regulator, which can effectively relieve the thermal stratification phenomenon to the wave tube and its main pipe nozzle while effectively connecting the voltage regulator to the main circuit. The impact of the office. The technical solution for implementing the present invention is as follows:
一种压水堆核电站稳压器竖直连接式波动管, 它包括竖直段 I、 竖直段 II, 以及上述两者之间的延伸段, 所述的竖直段 I从主回路管道的顶部竖直 接出, 所述的竖直段 II竖直向上与稳压器底部连接, 所述的延伸段与水平面 呈 2〜5°仰角向上延伸。  A vertically connected wave tube of a pressurized water reactor nuclear power plant voltage regulator, comprising a vertical section I, a vertical section II, and an extension between the two, the vertical section I from the main loop pipeline The top is vertically vertical, and the vertical section II is vertically connected to the bottom of the regulator, and the extension extends upward at an elevation angle of 2 to 5° from the horizontal plane.
在上述压水堆核电站稳压器竖直连接式波动管中: 所述的延伸段由直管 段、 弯曲段 I、 弯曲段 II和半圆段组成; 所述直管段的一端与主回路管道的 顶部竖直连接, 直管段的另一端与弯曲段 I连接; 所述的半圆段位于弯曲段 I和弯曲段 II之间; 所述的弯曲段 II的一端竖直向上与稳压器底部连接, 弯 曲段 II的另一端与半圆段连接。  In the vertical connection type surge tube of the above-mentioned pressurized water reactor nuclear power plant regulator: the extension section is composed of a straight pipe section, a curved section I, a curved section II and a semicircular section; one end of the straight pipe section and the top of the main circuit pipe Vertically connected, the other end of the straight pipe section is connected with the curved section I; the semicircular section is located between the curved section I and the curved section II; one end of the curved section II is vertically connected to the bottom of the regulator, and is bent The other end of the segment II is connected to the semicircular segment.
本发明所取得的有益效果如下: 利用设计的竖直段使得波动管从主管道 上竖直接出, 使得主管道上的波动管接管嘴焊缝上不存在热分层影响; 波动 管中间段的延伸段采用 2〜5°倾角向上延伸, 有效缓解了热分层效应对该段焊 缝的影响。  The beneficial effects obtained by the invention are as follows: The vertical section of the design is used to make the wave tube directly out of the main pipe, so that there is no thermal stratification on the weld of the wave tube nozzle on the main pipe; the extension of the middle section of the wave tube The upward extension of the inclination angle of 2~5° effectively alleviates the influence of the thermal stratification effect on the weld of the section.
附图说明  DRAWINGS
图 1为压水堆核电站稳压器竖直连接式波动管侧视图;  Figure 1 is a side view of a vertically connected surge tube of a pressurized water reactor nuclear power plant regulator;
图 2为图 1的俯视图;  Figure 2 is a plan view of Figure 1;
图中: 1.竖直段 I; 2.竖直段 Π ; 3.延伸段; 301.直管段; 302.半圆段; 303.弯曲段 I ; 304.弯曲段 II。  In the figure: 1. Vertical section I; 2. Vertical section Π; 3. Extension section; 301. Straight section; 302. Semi-circular section; 303. Curved section I; 304. Curved section II.
具体实施方式  detailed description
下面结合附图和具体实施例对本发明进行详细的描述。  The invention is described in detail below with reference to the drawings and specific embodiments.
如图 1所示, 波动管包括两段竖直段, 竖直段 I 1和竖直段 112, 还包括 两段竖直段 1和 2之间的延伸段 3,竖直段 I 1从主回路管道的顶部竖直接出, 因此该处的焊缝截面上不会存在热分层现象, 从而能够保证主管道与该处连 接后运行的安全和运行寿命。 另一竖直段 Π 2 竖直向上与稳压器底部连接, 实现主回路与稳压器的联通。 As shown in FIG. 1, the wave tube includes two vertical segments, a vertical segment I 1 and a vertical segment 112, and includes The extension 3 between the two vertical sections 1 and 2, the vertical section I 1 is vertically detached from the top of the main circuit duct, so that there is no thermal delamination on the weld section of the section, thereby ensuring the main The safety and operational life of the pipe running after it is connected. The other vertical section Π 2 is vertically connected to the bottom of the regulator to achieve communication between the main circuit and the regulator.
竖直段 1和 2之间的延伸段 3与水平面最优选择呈 2.5°仰角, 弯曲向上 倾斜延伸, 保持倾斜角度, 坡度足够大能够有效控制热分层现象对波动管的 延伸段 3的影响。  The extension 3 between the vertical sections 1 and 2 and the horizontal plane are optimally selected at an elevation angle of 2.5°, and the curved extension is inclined upward, maintaining the inclination angle, and the slope is sufficiently large to effectively control the influence of the thermal stratification on the extension 3 of the wave tube. .
本实施中, 延伸段 3的设计采用了一种最优形式, 如图 2所示, 延伸段 3 由四个部分组成, 直管段 301, 弯曲段 1 303和弯曲段 11304, 以及弯曲段 I 303和弯曲段 II 304之间的半圆段 302,四个部分组成了一种近似于 Ω形状 的管段。  In this embodiment, the design of the extension section 3 adopts an optimum form. As shown in FIG. 2, the extension section 3 is composed of four parts, a straight pipe section 301, a curved section 1303 and a curved section 11304, and a curved section I303. The semicircular section 302 between the curved section II 304 and the four sections constitute a section of the tube which approximates the omega shape.
显然, 本领域的技术人员可以对本发明进行各种改动和变型而不脱离本 发明的精神和范围。 倘若这些修改和变型属于本发明权利要求及其等同技术 的范围之内, 则本发明也意图包含这些改动和变型在内。  It is apparent that those skilled in the art can make various modifications and variations to the invention without departing from the spirit and scope of the invention. It is intended that the present invention covers such modifications and variations as such modifications and variations.

Claims

^ m ^ ^ ^ m ^ ^
1、一种压水堆核电站稳压器竖直连接式波动管, 其特征在于: 它包括竖 直段 I (1)、 竖直段 II (2), 以及上述两者之间的延伸段 (3), 所述的竖直 段 I (1) 从主回路管道的顶部竖直接出, 所述的竖直段 II (2) 竖直向上与 稳压器底部连接, 所述的延伸段 (3) 与水平面呈 2〜5°仰角向上延伸。 1. A vertically connected wave tube for a pressurized water reactor nuclear power station regulator, characterized in that: it includes a vertical section I (1), a vertical section II (2), and an extension section between the above two ( 3), the vertical section I (1) comes out vertically from the top of the main circuit pipe, the vertical section II (2) is connected vertically upward to the bottom of the voltage stabilizer, and the extension section (3 ) extends upward at an elevation angle of 2 to 5° with the horizontal plane.
2、如权利要求 1所述的压水堆核电站稳压器竖直连接式波动管,其特征 在于:所述的延伸段(3)由直管段(301)、弯曲段 I (303)、弯曲段 II (304) 和半圆段 (302) 组成; 所述直管段 (301) 的一端与主回路管道的顶部竖直 连接, 直管段(301)的另一端与弯曲段 I (303)连接; 所述的半圆段(302) 位于弯曲段 I (303)和弯曲段 II (304)之间; 所述的弯曲段 II (304) 的一 端竖直向上与稳压器底部连接, 弯曲段 II (304) 的另一端与半圆段 (302) 连接。 2. The vertically connected wave tube of a pressurized water reactor nuclear power station voltage stabilizer as claimed in claim 1, characterized in that: the extension section (3) consists of a straight pipe section (301), a curved section I (303), a curved section It consists of section II (304) and semicircular section (302); one end of the straight pipe section (301) is vertically connected to the top of the main loop pipeline, and the other end of the straight pipe section (301) is connected to the curved section I (303); so The semicircular section (302) is located between the curved section I (303) and the curved section II (304); one end of the curved section II (304) is connected vertically upward to the bottom of the voltage regulator, and the curved section II (304) ) The other end is connected with the semicircle segment (302).
PCT/CN2013/088417 2012-12-06 2013-12-03 Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant WO2014086274A1 (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB1511704.7A GB2523706B (en) 2012-12-06 2013-12-03 Vertical connection type surge pipe for pressurizer of pressurized water reactor nuclear power plant
ZA2015/04856A ZA201504856B (en) 2012-12-06 2015-07-06 Vertical connection type surge pipe for pressurizer of pressurized water reactor nuclear power plant

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN201210519796.2 2012-12-06
CN201210519796.2A CN103854709A (en) 2012-12-06 2012-12-06 Vertical connection type surge pipe for pressurized water reactor nuclear power plant voltage stabilizer

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WO2014086274A1 true WO2014086274A1 (en) 2014-06-12

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CN (1) CN103854709A (en)
AR (1) AR093808A1 (en)
GB (1) GB2523706B (en)
WO (1) WO2014086274A1 (en)
ZA (1) ZA201504856B (en)

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CN109798510A (en) * 2019-01-11 2019-05-24 中广核工程有限公司 A kind of main feed water pipe device for pressurized water reactor nuclear power station steam generator

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CN202650567U (en) * 2012-03-23 2013-01-02 中广核工程有限公司 Pressurizer surge line for nuclear power plant
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GB2523706B (en) 2017-12-06
GB201511704D0 (en) 2015-08-19
AR093808A1 (en) 2015-06-24
CN103854709A (en) 2014-06-11
GB2523706A (en) 2015-09-02
ZA201504856B (en) 2017-04-26

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