WO2016074436A1 - 热管道 - Google Patents

热管道 Download PDF

Info

Publication number
WO2016074436A1
WO2016074436A1 PCT/CN2015/076699 CN2015076699W WO2016074436A1 WO 2016074436 A1 WO2016074436 A1 WO 2016074436A1 CN 2015076699 W CN2015076699 W CN 2015076699W WO 2016074436 A1 WO2016074436 A1 WO 2016074436A1
Authority
WO
WIPO (PCT)
Prior art keywords
heat pipe
temperature
plane
temperature measuring
angle
Prior art date
Application number
PCT/CN2015/076699
Other languages
English (en)
French (fr)
Inventor
何向艳
陈军
宋磊
李冬生
周洲
蒋晓华
Original Assignee
中科华核电技术研究院有限公司
中国广核集团有限公司
中国广核电力股份有限公司
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 中科华核电技术研究院有限公司, 中国广核集团有限公司, 中国广核电力股份有限公司 filed Critical 中科华核电技术研究院有限公司
Priority to GB1603824.2A priority Critical patent/GB2534491B/en
Publication of WO2016074436A1 publication Critical patent/WO2016074436A1/zh

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/112Measuring temperature
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/017Inspection or maintenance of pipe-lines or tubes in nuclear installations
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • G21C17/022Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • 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 present invention relates to a nuclear power plant, and more particularly to a heat pipe for connecting a reactor pressure vessel to discharge water in a reactor pressure vessel.
  • the operating state of the nuclear reactor can be known by analyzing the state of the water temperature.
  • three or four temperature measurement points are usually arranged uniformly on the circumferential side of the heat pipe, and the temperature measured at the plurality of temperature measurement points is close to the actual temperature of the water in the heat pipe.
  • the existing water pipe temperature measurement method is relatively simple, and the simple average water temperature cannot accurately reflect the water temperature in the heat pipe, which is not conducive to the control of the nuclear power unit.
  • a new method for measuring the temperature of the hot water pipe is needed to improve the accuracy of the water temperature measurement of the hot pipe and to strengthen the control of the operation risk of the nuclear power unit.
  • the present invention discloses a heat pipe connected to a nuclear reactor pressure vessel, wherein the wall surface of the heat pipe is provided with a plurality of temperature measuring points; the horizontal plane of the heat pipe axis is a reference surface, along the a direction of fluid flow in the heat pipe, a portion of the reference surface located on the right side of the axis of the heat pipe is opposite to a plane passing through the axis of the heat pipe in a counterclockwise direction, and an angled plane of 25° and an angle of 35°
  • the temperature measurement point in the acute angle region is disposed on the reference surface side, and the temperature measurement point in the acute angle region between the 290° angle plane and the 310° angle plane is set on the reference
  • the number of the temperature measurement points in the area under the acute angle between the 25° angle plane and the 35° angle plane, and the acute angle between the 290° angle plane and the 310° angle plane The number of temperature measurement points within is equal.
  • the water temperature in the heat pipe is stratified, but the water temperature stratification is not simple, the high temperature water is on the upper side, and the low water temperature is on the lower side.
  • the cold zone in the heat pipe generally appears near the bottom of the heat pipe, and in the rare case occurs in the center of the heat pipe; the hot zone generally appears in the upper part of the hot pipe instead of the hot pipe. Top; the temperature at the junction of the cold zone and the hot zone is closer to the average temperature of the section, ie the temperature transition zone. Therefore, the placement of the temperature measurement points has a crucial influence on the accuracy of the temperature measurement results.
  • the heat pipe provided by the present invention is arranged with a temperature measuring point on the side of the temperature transition zone near the hot zone and the side close to the cold zone according to the water temperature distribution in the heat pipe, and the average temperature of the two temperature measuring points can reflect The average temperature in the heat pipe, the two temperature measurement points can also reflect the thermal fluctuations in the heat pipe, thereby strengthening the risk control of the nuclear power unit.
  • the temperature measurement point is further disposed between the 115° angle plane and the 125° angle plane, and the temperature measurement point between the 115° angle plane and the 125° angle plane is set in the The reference surface side; a temperature measurement point is arranged in the hot zone, so that the measured temperature can well reflect the high water temperature fluctuation of the heat pipe.
  • the temperature measuring point is further disposed between the 190° angle plane and the 230° angle plane, and the temperature measurement point between the 190° angle plane and the 230° angle plane is set on the reference.
  • the lower side of the surface; a temperature measuring point is arranged in the cold zone, so that the measured temperature can well reflect the low water temperature fluctuation of the heat pipe.
  • the number of temperature measuring points is four.
  • the sidewall of the heat pipe defines a temperature measuring hole, and any one of the temperature measuring holes constitutes the temperature measuring point.
  • the temperature measuring hole is connected with a temperature measuring nozzle; the temperature measuring nozzle directly measures the water temperature of the current temperature measuring point, and the measured temperature is relatively accurate.
  • the temperature measuring hole is connected with a water guiding pipe; the water guiding pipe leads the water of the current temperature measuring point to the mixed measurement in the temperature measuring bypass to improve the safety of the nuclear power component.
  • Figure 1 is a schematic view showing the connection of a reactor pressure vessel and a heat pipe.
  • FIG. 2 is a schematic view showing the distribution of temperature measurement points in the direction of fluid flow in the heat pipe.
  • the nuclear power unit includes a reactor pressure vessel 100 that communicates with the reactor pressure vessel 100 to discharge high temperature water absorbing nuclear heat energy from the reactor pressure vessel 100 for work. Due to the uneven distribution of heat release from the reactor core, the temperature distribution of the water in the outlet of the reactor pressure vessel 100 and the heat pipe 200 is uneven. As the flow distance of water in the heat pipe 200 increases, the water in the heat pipe 200 is stirred, and the temperature difference is gradually reduced, and is gradually stabilized after being 3 m from the outlet section of the reactor pressure vessel 100.
  • the temperature measurement point it is preferable to set the temperature measurement point to a region 3 m away from the outlet section of the nuclear reactor pressure vessel 100, where the water in the heat pipe 200 has been substantially stirred and the temperature distribution is relatively stable. It can better reflect the operation of nuclear power plants.
  • the water temperature is different such that water flows in the heat pipe 200 to produce stratification: the higher temperature water is located on the upper side of the heat pipe 200, and the lower temperature water is located on the lower side of the heat pipe 200.
  • a temperature transition zone located in the middle of the heat pipe 200 is formed between the higher temperature water and the lower temperature water.
  • the water temperature in the heat pipe 200 is stratified, but the water temperature stratification is not conventionally understood that the high temperature water is on the upper side and the low water temperature is on the lower side.
  • the cold zone in the heat pipe 200 generally appears near the bottom of the heat pipe 200, and less often in the center of the heat pipe 200; the hot zone generally appears in the heat pipe 200.
  • the upper part is inclined, not the top of the heat pipe 200; the temperature of the boundary between the cold zone and the hot zone is closer to the average temperature of the section, that is, the temperature transition zone. Therefore, the position of the temperature measurement point is stored in the accuracy of the temperature measurement result. The crucial impact.
  • the heat pipe 200 provided by the present invention is respectively arranged according to the water temperature distribution in the heat pipe 200, on the side close to the hot zone and the side close to the cold zone in the temperature transition zone.
  • a temperature measuring point, the average temperature of the two temperature measuring points can reflect the average temperature in the heat pipe 200, and the two temperature measuring points can also reflect the hot and cold fluctuations in the heat pipe 200, thereby strengthening the risk control of the nuclear power unit.
  • FIG. 2 the arrangement position of the temperature measuring points of the heat pipe 200 provided by the present invention is described in detail:
  • a portion of the reference surface 200A located on the right side of the axis of the heat pipe 200 is clipped counterclockwise with other planes passing through the axis of the heat pipe 200.
  • the plane is distinguished from the plane passing through the plane of the heat pipe 200 in a counterclockwise direction by a portion of the reference surface 200A located on the right side of the axis of the heat pipe 200, for example, on the right side of the axis of the heat pipe 200.
  • the portion of the reference surface 200A is at an angle of 25° with respect to the plane passing through the axis of the heat pipe 200 in the counterclockwise direction, and the plane passing through the axis of the heat pipe 200 is said to be an angle of 25°;
  • the angle between the 25° angle and the 35° is Two acute angle regions formed at opposite corners between the corner planes, wherein the wall of the heat pipe 200 in the acute angle region on the upper side of the reference plane 200A constitutes the first region 210;
  • the angle of 115° is opposite to 125°
  • the 190° angle plane and 230 ° Two acute angle regions formed at opposite corners between the corner planes, wherein the wall of the heat pipe 200 in the acute angle region on the lower side of the reference plane 200A constitutes the third region 230;
  • the heat pipe 200 provided by the invention has a plurality of temperature measuring points, the first area 210 and the fourth area 240 are respectively arranged with the same number of temperature measuring points, and the second area 220 and the third area 230 are set with temperature measuring points and temperature measuring.
  • the number of points is not limited.
  • the number of temperature measurement points is four.
  • the arrangement of the temperature measuring points on the heat pipe 200 of the present invention can be specifically divided into There are four cases: first, the first area 210 and the fourth area 240 are respectively arranged with two temperature measuring points, the second area 220 and the third area 230 are not arranged with temperature measuring points; second, the first area 210, the second The region 220, the third region 230, and the fourth region 240 are respectively disposed with one temperature measurement point; third, the first region 210 and the fourth region 240 are respectively disposed with one temperature measurement point, and the second region 220 is disposed with two temperature measurement points.
  • the third area 230 is not arranged with temperature measuring points; fourth, the first area 210 and the fourth area 240 are respectively arranged with one temperature measuring point, the second area 220 is not arranged with temperature measuring points, and the third area 230 is arranged with two Temperature measurement point.
  • the first region 210, the second region 220, the third region 230, and the fourth region 240 cover the cold zone, the hot zone, and the transition zone.
  • the above-mentioned arrangement scheme of the temperature measuring points takes care of each region. Even if the temperature field of the heat pipe 200 changes in a certain state during the transient process, the arrangement scheme can well reflect the average temperature of the water temperature in the heat pipe 200. And fluctuations.
  • the temperature measurement points disposed on the heat pipe 200 may be located in one cross section of the heat pipe 200, or may be located in different cross sections of the heat pipe 200, and the water temperature measurement result of the heat pipe 200 provided by the present invention may not be Have a big impact.
  • a temperature measuring hole is formed on the wall surface of the heat pipe 200 to form a temperature measuring point for measuring the water temperature in the heat pipe 200.
  • the temperature measuring nozzle is welded to the temperature measuring hole, and the temperature of the current temperature measuring point is directly measured by a temperature measuring device in the temperature measuring nozzle; in another embodiment, the water guiding pipe can also be connected.
  • the water inlet pipe draws a certain amount of water from each temperature measuring hole, and leads the extracted water to the temperature measuring bypass to mix and measure the temperature to obtain the water temperature data.
  • the heat pipe 200 of the present invention respectively arranges a temperature measuring point on a side close to the hot zone and a side close to the cold zone in the temperature transition zone, and the average temperature of the two temperature measuring points can reflect
  • the average temperature in the heat pipe 200 is set at a temperature measuring point in the cold zone and the hot zone, respectively, so that the measured temperature can well reflect the water temperature fluctuation of the heat pipe 200.
  • the heat pipe 200 provided by the present invention the cold zone, the hot zone and the transition zone in the heat pipe 200 are balanced, and even if the temperature field of the heat pipe 200 changes in a transient state, it can be well reflected.
  • the average temperature and fluctuation of the water temperature in the heat pipe 200 thereby strengthening the risk control of the nuclear power unit.

Landscapes

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

Abstract

一种热管道(200),连接于核反应堆压力容器(100),热管道(200)的壁面设置有若干个温度测量点;热管道(200)轴线所在的水平面为基准面(200A),顺着热管道(200)内流体流动方向,位于热管道(200)轴线右侧的部分基准面(200A)逆时针方向上与穿过热管道(200)轴线的平面成夹角,25°夹角平面与35°夹角平面之间所夹锐角区域(210)内的温度测量点的数量,与290°夹角平面与310°夹角平面之间所夹锐角区域(240)内的温度测量点的数量相等。该热管道将温度测量点以根据水温分层进行排布,从而使得测得温度接近实际温度,加强对核电机组的风险把控。

Description

热管道 技术领域
本发明涉及一种核电设备,尤其涉及一种用于连接反应堆压力容器以将反应堆压力容器内的水排出的热管道。
背景技术
通过检测经热管道排出的高温水的水温状态,通过分析水温状态可获知核反应堆的运行状态。现投入运行的核电机组中,通常于热管道的周侧均匀布置三个或四个温度测量点,多个温度测量点测得的温度即接近热管道中水的实际温度。
现有的热管道水温测量方式比较简单,单纯的平均水温不能精确反映热管道内的水温,不利于对核电机组的控制。
因此,需要一种新的热管道水温测量方式,提高对热管道水温测量的精度,加强对核电机组的运行风险把控。
发明内容
本发明的目的是提供一种热管道,其可以方便地测量热管道水温,同时提高热管道水温测量精度。
为了实现上述目的,本发明公开了一种热管道,连接于核反应堆压力容器,所述热管道的壁面设置有若干个温度测量点;所述热管道轴线所在的水平面为基准面,顺着所述热管道内流体流动方向,位于所述热管道轴线右侧的部分所述基准面逆时针方向上与穿过所述热管道轴线的平面成夹角,25°夹角平面与35°夹角平面之间所夹锐角区域内的所述温度测量点设置于所述基准面上侧,290°夹角平面与310°夹角平面之间所夹锐角区域内的所述温度测量点设置于所述基准面下侧,且25°夹角平面与35°夹角平面之间所夹锐角区域内的所述温度测量点的数量,与290°夹角平面与310°夹角平面之间所夹锐角区域内的所述温度测量点的数量相等。
通过热管道内的温度监测和计算发现,热管道内的水温分层,但该水温分层并非简单的高温水在上侧、低水温在下侧。根据对热管道内的温度监测和计算结果显示,热管道内的冷区一般出现在热管道的底部附近,较少情况下出现在热管道中心;热区一般出现在热管道斜上部,而非热管道顶部;冷区和热区交界线位置的温度较为接近截面平均温度,即温度过渡区。因此,温度测量点的布置位置对温度测量结果的精度存在至关重要的影响。对此,本发明提供的热管道根据热管道内的水温分布,于温度过渡区靠近热区的一侧和靠近冷区的一侧分别布置一温度测量点,该两温度测量点的平均温度能够反映热管道内的平均温度,该两温度测量点亦分别能够反映热管道内的冷热波动,从而加强对核电机组的风险把控。
较佳的,所述温度测量点还设置于115°夹角平面与125°夹角平面之间,且115°夹角平面与125°夹角平面之间的所述温度测量点设置于所述基准面上侧;于热区布置一温度测量点,使得测得的温度可以很好的反映热管道的高水温波动。
较佳的,所述温度测量点还设置于190°夹角平面与230°夹角平面之间,190°夹角平面与230°夹角平面之间的所述温度测量点设置于所述基准面下侧;于冷区布置一温度测量点,使得测得的温度可以很好的反映热管道的低水温波动。
较佳的,所述温度测量点的数量为四个。
较佳的,任一所述温度测量点与所述核反应堆压力容器的出口截面间的距离均大于3m;流体流出核反应堆压力容器、进入热管道后,随着流动距离的增加,温差逐渐减小,并在距离压力容器出口截面3m以后的位置区域逐渐稳定,将温度测量点设置于距核反应堆压力容器的出口截面3m以后的区域,热管道内水的温度分布已逐渐稳定,测得的温度较平稳,更能反映核电机组的运行情况。
较佳的,所述热管道的侧壁开设测温孔,任一所述测温孔构成所述温度测量点。
具体地,所述测温孔连接有测温接管嘴;测温接管嘴直接测得当前温度测量点的水温,测得温度比较准确。
具体地,所述测温孔连接有引水管;引水管将当前温度测量点的水引出至测温旁路中混合测量,提高核电组件的安全性。
附图说明
图1为反应堆压力容器与热管道的连接示意图。
图2为热管道内流体流动方向上温度测量点的分布示意图。
具体实施方式
为详细说明本发明的技术内容、构造特征、所实现目的及效果,以下结合实施方式并配合附图详予说明。
如图1所示,核电机组包括反应堆压力容器100,热管道200连通于反应堆压力容器100以将吸收核热能的高温水排出反应堆压力容器100进行做功。由于反应堆堆芯释热分布不均,导致反应堆压力容器100出口和热管道200内水的温度分布不均。随着水在热管道200内流动距离的增加,热管道200内的水发生搅混,温差逐渐减小,在距反应堆压力容器100出口截面3m以后逐渐稳定。因此,本发明提供的热管道200,优选的,将温度测量点设置于距核反应堆压力容器100的出口截面3m以后的区域,此处热管道200内的水已基本完成搅混,温度分布较平稳,更能反映核电机组的运行情况。
在常规理解中,热管道200内的水流截面中,水温不同使得水流于热管道200内产生分层:温度较高的水位于热管道200上侧,温度较低的水位于热管道200下侧,于温度较高的水和温度较低的水之间,形成位于热管道200中部的温度过渡区。
通过热管道200内的温度监测和计算发现,热管道200内的水温分层,但该水温分层并非常规理解中的高温水在上侧、低水温在下侧。根据对热管道200内的温度监测和计算结果显示,热管道200内的冷区一般出现在热管道200的底部附近,较少情况下出现在热管道200中心;热区一般出现在热管道200斜上部,而非热管道200顶部;冷区和热区交界线位置的温度较为接近截面平均温度,即温度过渡区。因此,温度测量点的布置位置对温度测量结果的精度存 在至关重要的影响。
为使得温度测量结果接近热管道200内的实际平均温度,本发明提供的热管道200根据热管道200内的水温分布,于温度过渡区靠近热区的一侧和靠近冷区的一侧分别布置一温度测量点,该两温度测量点的平均温度能够反映热管道200内的平均温度,该两温度测量点亦分别能够反映热管道200内的冷热波动,从而加强对核电机组的风险把控。结合图2所示,对本发明提供的热管道200的温度测量点的布置位置详细说明:
以热管道200轴线所在的水平面为基准面200A,顺着热管道200内流体流动方向,位于热管道200轴线右侧的部分基准面200A逆时针方向上与穿过热管道200轴线的其他平面成夹角;为方便说明,以位于热管道200轴线右侧的部分基准面200A逆时针方向上与穿过热管道200轴线的平面所成夹角的度数加以区分平面,如,位于热管道200轴线右侧的部分基准面200A逆时针方向上与穿过热管道200轴线的平面于成夹角为25°,称该穿过热管道200轴线的平面为25°夹角平面;25°夹角平面与35°夹角平面之间形成的呈对顶角的两个锐角区域,其中,位于基准面200A上侧的一所述锐角区域内的热管道200壁面构成第一区域210;115°夹角平面与125°夹角平面之间形成的呈对顶角的两个锐角区域,其中,位于基准面200A上侧的一所述锐角区域内的热管道200壁面构成第二区域220;190°夹角平面与230°夹角平面之间形成的呈对顶角的两个锐角区域,其中,位于基准面200A下侧的一所述锐角区域内的热管道200壁面构成第三区域230;290°夹角平面与310°夹角平面之间形成的呈对顶角的两个锐角区域,其中,位于基准面200A下侧的一所述锐角区域内的热管道200壁面构成第四区域240;;温度测量点布置于热管道200的壁面,且温度测量点布置于第一区域210、第二区域220、第三区域230和第四区域240。本发明提供的热管道200具有若干个温度测量点,第一区域210和第四区域240分别布置有数量相同的温度测量点,第二区域220和第三区域230是否设置温度测量点及温度测量点的数量均未加以限定。
较佳的,温度测量点的数量为4个。根据上述对本发明热管道200上温度测量点的布置位置的说明,本发明热管道200上温度测量点的排布可具体分为 四种情况:第一,第一区域210和第四区域240分别布置有两个温度测量点,第二区域220和第三区域230未布置温度测量点;第二,第一区域210、第二区域220、第三区域230和第四区域240分别布置有一个温度测量点;第三,第一区域210和第四区域240分别布置有一个温度测量点,第二区域220布置有两个温度测量点,第三区域230未布置温度测量点;第四,第一区域210和第四区域240分别布置有一个温度测量点,第二区域220未布置温度测量点,第三区域230布置有两个温度测量点。
根据本发明提供的热管道200,第一区域210、第二区域220、第三区域230和第四区域240涵盖了冷区、热区和过渡区。上述的温度测量点的布置方案,对各区域均加以兼顾,即便在瞬态过程中热管道200温度场有一定的变化,该布置方案仍可以很好的反映出热管道200内水温的平均温度和波动。
进一步的,布置于热管道200上的温度测量点可以位于热管道200的一个横截面内,亦可位于热管道200的不同横截面内,其对本发明提供的热管道200的水温测量结果不会产生较大的影响。
较佳的,于热管道200壁面的上开设测温孔形成温度测量点,以便对热管道200内的水温进行测量。在一实施例中,测温接管嘴焊接于测温孔上,通过测温接管嘴内的温度测量器直接测量获得当前温度测量点的温度;在另一实施例中,亦可将引水管连接于测温孔上,引水管分别自各测温孔引出一定量的水,并将引出的水引至测温旁路中混合后测量温度获得水温数据。核通过分析水温测量数据,从而方便、准确地了解核电机组的运行状态,加强对核电机组的风险把控。
本发明提供的热管道200根据热管道200内的水温分布,于温度过渡区靠近热区的一侧和靠近冷区的一侧分别布置一温度测量点,该两温度测量点的平均温度能够反映热管道200内的平均温度,分别于冷区和热区设置一温度测量点,使得测得的温度可以很好的反映热管道200的水温波动。根据本发明提供的热管道200,对热管道200内的冷区、热区和过渡区均加以兼顾,即便在瞬态过程中热管道200温度场有一定的变化,仍可以很好的反映出热管道200内水温的平均温度和波动,从而加强对核电机组的风险把控。
以上所揭露的仅为本发明的优选实施例而已,当然不能以此来限定本发明之权利范围,因此依本发明申请专利范围所作的等同变化,仍属本发明所涵盖的范围。

Claims (8)

  1. 一种热管道,连接于核反应堆压力容器,其特征在于:所述热管道的壁面设置有若干个温度测量点;所述热管道轴线所在的水平面为基准面,顺着所述热管道内流体流动方向,位于所述热管道轴线右侧的部分所述基准面逆时针方向上与穿过所述热管道轴线的平面成夹角,25°夹角平面与35°夹角平面之间所夹锐角区域内的所述温度测量点设置于所述基准面上侧,290°夹角平面与310°夹角平面之间所夹锐角区域内的所述温度测量点设置于所述基准面下侧,且25°夹角平面与35°夹角平面之间所夹锐角区域内的所述温度测量点的数量,与290°夹角平面与310°夹角平面之间所夹锐角区域内的所述温度测量点的数量相等。
  2. 如权利要求1所述的热管道,其特征在于:所述温度测量点还设置于115°夹角平面与125°夹角平面之间,且115°夹角平面与125°夹角平面之间的所述温度测量点设置于所述基准面上侧。
  3. 如权利要求1所述的热管道,其特征在于:所述温度测量点还设置于190°夹角平面与230°夹角平面之间,190°夹角平面与230°夹角平面之间的所述温度测量点设置于所述基准面下侧。
  4. 如权利要求1所述的热管道,其特征在于:所述温度测量点的数量为四个。
  5. 如权利要求1所述的热管道,其特征在于:任一所述温度测量点与所述核反应堆压力容器的出口截面间的距离均大于3m。
  6. 如权利要求1所述的热管道,其特征在于:所述热管道的侧壁开设测温孔,任一所述测温孔构成所述温度测量点。
  7. 如权利要求6所述的热管道,其特征在于:所述测温孔连接有测温接管嘴。
  8. 如权利要求6所述的热管道,其特征在于:所述测温孔连接有引水管。
PCT/CN2015/076699 2014-11-11 2015-04-16 热管道 WO2016074436A1 (zh)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB1603824.2A GB2534491B (en) 2014-11-11 2015-04-16 Hot-water pipe

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN201410631637.0 2014-11-11
CN201410631637.0A CN104376882B (zh) 2014-11-11 2014-11-11 热管道

Publications (1)

Publication Number Publication Date
WO2016074436A1 true WO2016074436A1 (zh) 2016-05-19

Family

ID=52555742

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/CN2015/076699 WO2016074436A1 (zh) 2014-11-11 2015-04-16 热管道

Country Status (3)

Country Link
CN (1) CN104376882B (zh)
GB (1) GB2534491B (zh)
WO (1) WO2016074436A1 (zh)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2019112727A1 (en) * 2017-12-04 2019-06-13 Westinghouse Electric Company Llc Heat pipe assembly of nuclear apparatus having fiber optical temperature detection system

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104376882B (zh) * 2014-11-11 2017-03-22 中广核研究院有限公司 热管道
CN208400506U (zh) * 2018-07-03 2019-01-18 中广核研究院有限公司 核反应堆回路测温热管道及测温装置
GB2581407B (en) * 2018-07-03 2022-12-07 China Nuclear Power Technology Res Inst Co Ltd Temperature measuring device in a nuclear reactor loop

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2003270378A (ja) * 2002-03-12 2003-09-25 Toshiba Corp 原子力発電所のサプレッションプール温度監視装置
JP2007205799A (ja) * 2006-01-31 2007-08-16 Toshiba Corp 沸騰水型原子炉の冷却材温度測定装置およびその測定方法
CN103824604A (zh) * 2013-11-18 2014-05-28 国核(北京)科学技术研究院有限公司 堆芯紧急冷却热混合试验装置及其试验方法
CN104376882A (zh) * 2014-11-11 2015-02-25 中科华核电技术研究院有限公司 热管道
CN104464851A (zh) * 2014-12-19 2015-03-25 大连理工大学 一种用于核电站一回路高温管道热疲劳原型监测装置及其监测方法
CN204242603U (zh) * 2014-11-11 2015-04-01 中科华核电技术研究院有限公司 热管道温度测量套管

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP3649223B2 (ja) * 2003-01-08 2005-05-18 株式会社日立製作所 配管系の熱処理方法および熱処理装置
CN102840930B (zh) * 2012-08-21 2014-06-04 清华大学 管道内部温度测量装置
DE202013103059U1 (de) * 2013-07-10 2013-09-27 Temperaturmeßtechnik Geraberg GmbH Thermoelektrisches Temperaturmessmodul zur Messung der Temperatur in einer Rohrleitung mit Doppelmessstelle
CN104007134B (zh) * 2014-05-23 2016-03-09 中国石油化工股份有限公司 热介质输送管道及其敷设环境的温度测量系统
CN204242604U (zh) * 2014-11-11 2015-04-01 中科华核电技术研究院有限公司 热管道

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2003270378A (ja) * 2002-03-12 2003-09-25 Toshiba Corp 原子力発電所のサプレッションプール温度監視装置
JP2007205799A (ja) * 2006-01-31 2007-08-16 Toshiba Corp 沸騰水型原子炉の冷却材温度測定装置およびその測定方法
CN103824604A (zh) * 2013-11-18 2014-05-28 国核(北京)科学技术研究院有限公司 堆芯紧急冷却热混合试验装置及其试验方法
CN104376882A (zh) * 2014-11-11 2015-02-25 中科华核电技术研究院有限公司 热管道
CN204242603U (zh) * 2014-11-11 2015-04-01 中科华核电技术研究院有限公司 热管道温度测量套管
CN104464851A (zh) * 2014-12-19 2015-03-25 大连理工大学 一种用于核电站一回路高温管道热疲劳原型监测装置及其监测方法

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2019112727A1 (en) * 2017-12-04 2019-06-13 Westinghouse Electric Company Llc Heat pipe assembly of nuclear apparatus having fiber optical temperature detection system

Also Published As

Publication number Publication date
GB201603824D0 (en) 2016-04-20
CN104376882B (zh) 2017-03-22
GB2534491B (en) 2020-10-14
CN104376882A (zh) 2015-02-25
GB2534491A (en) 2016-07-27

Similar Documents

Publication Publication Date Title
WO2016074436A1 (zh) 热管道
Dhungel et al. Film cooling from a row of holes supplemented with antivortex holes
Barigozzi et al. Fan-shaped hole effects on the aero-thermal performance of a film-cooled endwall
CN105526997B (zh) 一种液态金属流量计标定容器、标定回路及标定方法
CN103836800B (zh) 电热水器及其控制方法
WO2016074410A1 (zh) 热管道温度测量套管
CN111141400B (zh) 核电站弯管热疲劳敏感区管壁温度测量方法
Chi et al. Geometrical optimization and experimental validation of a tripod film cooling hole with asymmetric side holes
CN105651534B (zh) 一种可实现高压与低压燃油滑油散热器试验的系统
CN106816190B (zh) 核电站反应堆主管道冷却剂温度测量系统以及方法
Zhang et al. The effects of vane showerhead injection angle and film compound angle on nozzle endwall cooling (phantom cooling)
CN207113940U (zh) 喉部取压长颈喷嘴节流装置
US8457937B2 (en) Method of optimizing volume utilization of an autoclave
Han et al. The heat/mass transfer analogy for a simulated turbine endwall
CN204242604U (zh) 热管道
CN105136342B (zh) 微温差条件下提高换热器换热量测量精度的系统及方法
CN207515915U (zh) 一种高温器械用温度仪表
Luque et al. A new experimental facility to investigate combustor-turbine interactions in gas turbines with multiple can combustors
Chi et al. Geometrical optimization and experimental validation of a tripod film cooling hole with asymmetric side holes
CN103706996A (zh) 避免混流式水轮机转轮叶片出现裂纹的方法
CN103091119B (zh) 一种液体空化加热设备输出热效率测试方法及装置
CN104990834B (zh) 一种发动机的冷却液中的空气含量的测量装置及方法
WO2020006915A1 (zh) 核反应堆回路测温热管道及测温装置
CN203321732U (zh) 用于共轨泵高压流量测量前的燃油温度调控装置
CN105571842B (zh) 一种航空发动机导流器新型试验装置

Legal Events

Date Code Title Description
ENP Entry into the national phase

Ref document number: 201603824

Country of ref document: GB

Kind code of ref document: A

Free format text: PCT FILING DATE = 20150416

121 Ep: the epo has been informed by wipo that ep was designated in this application

Ref document number: 15858582

Country of ref document: EP

Kind code of ref document: A1

NENP Non-entry into the national phase

Ref country code: DE

32PN Ep: public notification in the ep bulletin as address of the adressee cannot be established

Free format text: NOTING OF LOSS OF RIGHTS PURSUANT TO RULE 112(1) EPC (EPO FORM 1205A DATED 02/10/2017)

122 Ep: pct application non-entry in european phase

Ref document number: 15858582

Country of ref document: EP

Kind code of ref document: A1