GB2581407A - Nuclear reactor loop temperature measurement heat pipe and temperature measurement device - Google Patents

Nuclear reactor loop temperature measurement heat pipe and temperature measurement device Download PDF

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Publication number
GB2581407A
GB2581407A GB1907946.6A GB201907946A GB2581407A GB 2581407 A GB2581407 A GB 2581407A GB 201907946 A GB201907946 A GB 201907946A GB 2581407 A GB2581407 A GB 2581407A
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GB
United Kingdom
Prior art keywords
heat pipe
temperature measurement
temperature
central axis
pipe body
Prior art date
Legal status (The legal status 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 status listed.)
Granted
Application number
GB1907946.6A
Other versions
GB2581407B (en
GB201907946D0 (en
Inventor
Song Lei
Hu Yousen
Li Changying
Wang Xiaotong
Zhou Youxin
Zhu Jianmin
Mao Yulong
Ye Liang
Zheng Wenqiang
Rui Min
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
Original Assignee
China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
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
Priority claimed from CN201821059726.2U external-priority patent/CN208400506U/en
Application filed by China General Nuclear Power Corp, China Nuclear Power Technology Research Institute Co Ltd, CGN Power Co Ltd filed Critical China General Nuclear Power Corp
Publication of GB201907946D0 publication Critical patent/GB201907946D0/en
Publication of GB2581407A publication Critical patent/GB2581407A/en
Application granted granted Critical
Publication of GB2581407B publication Critical patent/GB2581407B/en
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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
    • G01K1/00—Details of thermometers not specially adapted for particular types of thermometer
    • G01K1/14—Supports; Fastening devices; Arrangements for mounting thermometers in particular locations
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
    • G01K13/00—Thermometers specially adapted for specific purposes
    • G01K13/02—Thermometers specially adapted for specific purposes for measuring temperature of moving fluids or granular materials capable of flow
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
    • G01K13/00—Thermometers specially adapted for specific purposes
    • G01K13/02—Thermometers specially adapted for specific purposes for measuring temperature of moving fluids or granular materials capable of flow
    • G01K13/026—Thermometers specially adapted for specific purposes for measuring temperature of moving fluids or granular materials capable of flow of moving liquids
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/112—Measuring temperature
    • 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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  • Physics & Mathematics (AREA)
  • General 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

Disclosed is a nuclear reactor loop temperature measurement heat pipe, comprising a heat pipe main body, wherein the heat pipe main body has a cross section in the horizontal direction of a ring structure, and has a cross section in the vertical direction and passing through a central axis of a cylinder structure; an accommodation cavity is formed in the middle of the heat pipe main body, and a flow channel is formed on the periphery; and a side wall of the heat pipe main body is provided with several temperature measurement water drawing holes, and the temperature measurement water drawing holes are arranged around the central axis of the heat pipe main body and at a same horizontal height.

Description

HEAT PIPE FOR MEASURING TEMPERATURE IN NUCLEAR REACTOR LOOP AND TEMPERATURE MEASURING DEVICE
FIELD OF THE INVENTION
100011 The present invention relates to a temperature measuring equipment in a nuclear reactor loop and, more particularly to a heat pipe for measuring temperature in a nuclear reactor loop and a temperature measuring device.
BACKGROUND OF THE INVENTION
[0002] In order to realize the functions of the reactor control and protection system, it is necessary to measure the average temperature of the coolant in the primary loop. The temperature signal must be able to respond quickly to the temperature change of the primary loop. However, the coolant in the primary loop has temperature stratification. The difference of the coolant temperature at different positions is large, and the fluctuation of the average mperature measurement value of the coolant in the primary loop heat pipe is great due to a poor arrangement of the heat pipe and temperature measuring device, therefore the measurement accuracy is low. Especially for a compact reactor, it's desirable that the temperature measuring device or the loop arrangement occupies less space, thus it's difficult and important to optimize the heat pipe and the temperature in easuring device.
SUMMARY OF THE INVENTION
[0003] One objective of the present invention is to provide a heat pipe for measuring temperature in a nuclear reactor loop, which has compact structure to save space, can measure temperature quickly, improve the temperature measurement accuracy and reduce data fluctuation for measured temperature.
[0004] Another objective of the present invention is to provide a temperature measuring device in a nuclear reactor loop, which can measure ature quickly, improve the temperature measurement accuracy and reduce data fluctuation for measured temperature.
[0005] To achieve the above-mentioned objectives, the present ntion provides a heal pipe for measuring temperature in a nuclear reactor loop, comprising a heat pipe body, a cross section of the heat pipe body in a direction perpendicular to a central axis thereof being a ring structure, and a section of the heat pipe body in a length direction thereof being a cylinder structure, a cavity being defined at a center of the heat pipe body, a flow passage being formed around the cavity a side wall of the heat pipe body being provided with multiple temperature measurement positions arranged around a central axis of the heat pipe body and located at a same level.
100061 In comparison with the prior since the cross section of tl pipe body in the direction perpendicular to the central axis thereof is a ring structure, and a section of the heat pipe body 1 in the length direction thereof is a cylinder structure, thus the simple structure can benefit to reduce arrangement space after such a heat pipe body I_ is installed at the primary side of the steam generator of the nuclear reactor, so as to achieve a compact arrangement for the nuclear reactor. Additionally, the multiple temperature measurement positions are provided at the side wall of the heat pipe body" around the central axis of the heat pipe body and located at the same level, so as to quickly perform temperature measurement to the heat pipe at different positions. As the amount of the temperature measurement positions is increased, the measurement error is reduced to efficiently improve the accuracy of the temperature measurement.
[0007] Preferably, a distance between each temperature measurement position and an upper surface of the heat pipe body is in a range of 500mm-800mm. At this height, the temperature difference of the coolant of the primary loop is small, and the temperature fluctuation is stnall, thereby die temperature measurement fluctuation is reduced efficiently.
[0008] Preferably, the heat pipe body is provided with an entry communicated with an inlet pipe on a primary side of a steam generator.
100091 Preferably, the central axis of the heat pipe body is vertical to a central axis of the entry, and a symmetry plane of the heat pipe body is established between the two central axes.
[00101 Preferably, the temperature measurement positions located at two sides of the symmetry plane are configured symmetrically.
[0011] Preferably', the temperature measurement positions comprises a first temperature measurement position closely to the entry, and an angle between a central axis of the first temperature measurement position and the central axis of the entry in a horizontal projection is in a range of 24-42 degrees.
[00121 Preferably, the temperature measurement positions further comprises multiple second temperature measurement positions, an angle between a central axis of the first temperature measurement position and a central axis of the second temperature measurement position which is close to the first temperature measure position is larger than that between central axis of the first temperature measurement position and the central axis of the entry.
[00131 Preferably, the temperature measuring unit is arranged to perform temperature measurement at the temperature measurement positions.
[00141 Preferably, the temperature measuring unit is fixed at the temperature measurement positions.
100151 Preferably, a pipeline is configured between the temperature measuring unit and the temperature measurement positions to direct tested coolant.
BRIE1-DESCRIPTION OF THE DRAWINGS
100161 The accompanying drawings facilitate an understanding of the various embodiments of this invention, In such drawings: [0017I 1 is a sectional view of a heat pipe for measuring temperature in a ran ear reactor loop according to the present invention; 100181 Fig. 2 is a top view of a heat pipe for measwing mperature in a nuclear reactor loop according to the present invention; [00191 Fig. 3 is a schematic view of the temperature measurement positions according to a first embodiment; [00201 Fig. 4 is a schematic view of the temperature measurement positions according to a second embodiment; and [00211 Fig. 5 is a schematic vies of the temperature measurement positions according to a third embodiment.
DETAILED DESCRIPTION OF ILLUSTRATED EMBODIMENTS
[00221 Various preferred embodiments of the invention will now be described with reference to the figures, wherein like reference numerals designate similar parts throughout the various views.
[00231 Referring to Figs. 1 and 2, a temperature measuring device in a nuclear reactor loop according to the present invention includes a temperature measuring unit and a heat pipe 100. The heat pipe 100 is amounted on upstream of a heat exchange tube bundle on the primary' side of a nuclear reactor steam generator,and the heat pip:. 100 includes a heat pipe body I. Specifically, a cross section of the heat pipe body 100 in a direction perpendicular to a central axis of the heat pipe body 100 is a ring structure, and a section of the heat pipe body 100 in a length direction of the heat pipe body and passing through the central axis thereof is a cylinder structure, such a.s an inverted II-shaped structure. A cavity 11 is formed in the center of the heal pipe body 1 for receiving the heat exchange tube bundle, a flow passage 12 is formed around the cavity 11, multiple temperature measurement positions 13 are formed on a side wall of the heat pipe body 1 and around the central axis of the heat pipe body 1, and the temperature measurement positions 13 are located at the same level. An entry 14 is formed on the heat pipe body 1 to communicate with an inlet pipe 2 of the primary side of the steam generator, and the flow passage 12 respectively. The temperature measuring unit is fixed at the temperature measurement position 13 to measure the temperature of the coolant in the primary loop directly. Of course, a pipe may he disposed between the temperature measuring unit and the temperature measurement position 13, and the coolant can be taken out to a main pipe by the pipe, and then the temperature measuring unit performs the temperature measurement through the main pipe to the heat pipe body 1.
[0024] More specifically, the central axis of the heat pipe body 1 is vertical to the central axis of the entry 1.4, and a symmetry plane A of the heat pipe body I is formed between Ilk, two central axes. The temperature mcasurein.ent positions 13 located at two sides of the symmetry plane A are configured symmetrically.
[0025] The distance k between the temperature measurement positions 13 and the upper end surface of the heat pipe body 1 is in a range of 500itn to 800min. At this height, the temperature difference of the coolant of the primary loop is small, and the temperature fluctuation is small, thereby the temperature measurement fluctuation is reduced efficiently.
100261 The temperature measurement positions 13 includes first temperature measurement positions 131 and multiple second temperature measurement positions 132, the angle between the central axis of the first temperature measurement position 131 and the central axis of the second temperature measurement position 132 winch is close to the first temperature measure position 131 is larger than the angle between the central axis of the first temperature measurement position 131 and the central axis of the entry 14. There are multiple arrangements of the temperature measurement positions 13 at the same level, as follow, for example.
[0027] As illustrated in Fig. 3, a first embodiment of the temperature measurement positions 13 is shown.
[00281 The temperature measurement positions 13 located at a side of the symmetry plane A includes a first temperature measurement position 131 and the second temperature measurement position 132, the first temperature measurement position 131 is closer to the entry 14 than the second temperature measurement position 132, the central axis of the first temperature measurement position 13 is located at the radial direction of the heat pipe body 1, an angle a between the central axis of the first temperature measurement position 13 and the central axis of the entry 14 in the horizontal projection is in a range of 30-42 degrees, and an angle b between the second temperature measurement position 132 and the first temperature measurement position 131 is 90 degrees. Symmetrically, in the opposite side of the symmetry plane A, the arrangements of the angle a between the first temperature measurement position 13 and the 14 and the angle b between the temperature measurement position i 3 and the second temperature measurement position 132 are the same.
[0029] As illustrated in Fig. 4, a second embodiment of the temperature measurement positions 13 is shown.
[0030] The temperature measurement positions 13 located at one side of the symmetry plane A includes a first temperature measurement position 131 and two second temperature measurement positions 132, the first temperature measurement position 131 is closer to the entry 14 than the second temperature measurement positions 132, the central axis of the first temperature measurement position 13 is located at the radial direction of the heat pipe body I, an angle c between the central axis of the first temperature measurement position 13 and the central axis of the entry 14 in the horizontal projection is in a range of 26-35 degrees, an angle d between the second temperature measurement position 132 which is closer to the first temperature measurement position 131 and the first temperature measurement position 131 is 60 degrees, and an angle e between another second temperature measurement position 132 and the previous second temperature measurement position 132 is 60 degrees. Symmetrically, in the opposite side of the symmetry plane A, the arrangements of the angle c between the first temperature measurement position 13 and the 14, lie angle d between the first temperature measurement position 13 and the second temperature measurement position 132, and the angle e between the two second temperature measurement positions 132 are the same.
[0031] As illustrated in 5, a third embodiment of the temperature measurement positions 13 is shown.
[0032] The temperature measurement positions 13 located at one side of the symmetry plane A includes a first temperature measurement position 131 and three second temperature measurement positions 132, the first temperature measurement position 131 is closer to the entry 14 than the second temperature measurement positions 132, the central axis of the first temperature measurement position 13 is located at the radial direction of the heat pipe body 1, an angle f between the central axis of the first temperature measurement position 13 and the central axis of the entry t4 in the horizontal projection is in a range of 24-30 degrees, an angle g between the first temperature measurement position 131 and the second temperature measurement position 132 which is closer to the first temperature measurement position 131 is 45 degrees, and an angle h between two adjacent second temperature measurement positions 132 is 45 degrees. Symmetrically, in the opposite side of the symmetry plane A, the arrangements of the angle f between the first temperature measurement position 13 and the entry 14, the angle g between the first temperature measurement position 131 and the second temperature measurement position 132, and the angle g between the two adjacent second temperature measurement positions 132 are the same.
100331 In comparison with the prior art, since the cross section of the heat pipe body I in the direction perpendicular to the central axis thereof is a ring structure, and a section of the heat pipe body 1 in the length direction thereof is a cylinder structure, thus the simple structure can benefit to reduce arrangement space after such a heat pipe body 1 is installed at the primary side of the steam generator of the nuclear reactor, so as to achieve a compact arrangement for the nuclear reactor. Additionally" the multiple temperature measurement positions are provided at the side wall of the heat pipe body 1, around the central axis of the heat pipe body 1 and located at the same level, so as to quickly perform temperature measurement to the heat pipe at different positions. As the amount of the temperature measurement positions is increased, the measurement error is reduced to efficiently improve the accuracy of the temperature measurement.
[0034] While the invention has been described in connection with what are presently considered to be the most practical and preferred embodiments, it is to be understood that the invention is not to be limited to the disclosed embodiments, but on the contrary, is intended to cover various modifications and equivalent arrangements included within the spirit and scope of the invention.

Claims (10)

  1. WHAT IS CLAIMED1. A heat pipe for measuring temperature in a nuclear reactor loop, comprising a heat pipe body, a cross section of the heat pipe body in a direction perpendicular to a central axis thereof being a ring structure, and a section of the heat pipe body in a length direction thereof being a cylinder structure, a. cavity being defined at a. center of the heat pipe body, a. flow passage being formed around the ca and a side wall of the heat pipe body being provided with multiple temperature measurement positions arranged around a central axis of the heat pipe body and located at a same level.
  2. 2. The heat pipe for measuring temperature in a nuclear reactor loop according to claim 1, wherein a distance between each temperature measurement position and an upper surface of the heat pipe body is in a range of 500min-800m m J.
  3. The heat pipe for measuring temperature in a nuclear reactor loop according to claim 1, wherein the heat pipe body is provided with an entry communicated with an inlet pipe on a primary side of a steam generator.
  4. 4. The heat pipe for measuring temperature in a nuclear reactor loop according to claim 3, wherein the central axis of the heat pipe body is vertical to a central axis of the entry, and a symmetry plane of the heat pipe body is established between the two central axes.
  5. 5. The heat pipe for measuring temperature in a nuclear reactor loop according to claim 4, wherein the temperature measurement positions located at two sides of the symmetry plane are configured symmetrically.
  6. 6. The heat pipe for measuring temperature in a nuclear reactor loop according to claim 5, wherein the temperature measurement positions comprises a first temperature measurement position closely to the entry, and an angle between a central axis of the first temperature measurement position and the central axis of the entry in a horizontal projection is in a range of 24-42 degrees.
  7. 7. The heat pipe for measuring temperature in a nuclear reactor loop according to claim 6, wherein the temperature measurement positions further comprises multiple second temperature measurement positions, an angle between a central axis of the first temperature measurement position and a central axis of the second temperature measurement position which is close to the first temperature measure position is larger than that between al axis of the first temperature measurement position and the central axis of the entry.
  8. 8. A temperature measuring device in a nuclear reactor loop, comprising temperature measuring unit and the heat pipe according to any one of claims 1-7, wherein the temperature measuring unit is arranged to perform temperature measurement at the temperature measurement positions.
  9. 9. The temperature measuring device in a nue!ear reactor loop according to claim 8, wherein the temperature measuring unit is fixed at the temperature measurement positions.
  10. 10. The temperature measuring device in a nuclear eactor loop according to claim 8, wherein a. pipeline is configured between the erature measuring unit and the temperature measurement positions to direct tested coolant. t
GB1907946.6A 2018-07-03 2018-09-30 Temperature measuring device in a nuclear reactor loop Active GB2581407B (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN201821059726.2U CN208400506U (en) 2018-07-03 2018-07-03 Nuclear reactor circuit thermometric heat pipeline and temperature measuring equipment
PCT/CN2018/108963 WO2020006915A1 (en) 2018-07-03 2018-09-30 Nuclear reactor loop temperature measurement heat pipe and temperature measurement device

Publications (3)

Publication Number Publication Date
GB201907946D0 GB201907946D0 (en) 2019-07-17
GB2581407A true GB2581407A (en) 2020-08-19
GB2581407B GB2581407B (en) 2022-12-07

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GB1907946.6A Active GB2581407B (en) 2018-07-03 2018-09-30 Temperature measuring device in a nuclear reactor loop

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Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5948934B2 (en) * 1981-05-30 1984-11-29 新日本製鐵株式会社 Manufacturing method of high magnetic flux density unidirectional electrical steel sheet
CN104376882A (en) * 2014-11-11 2015-02-25 中科华核电技术研究院有限公司 Hot pipeline
CN104464851A (en) * 2014-12-19 2015-03-25 大连理工大学 Device and method for monitoring thermal fatigue prototype of loop high-temperature pipeline in nuclear power plant
CN105359220A (en) * 2013-05-28 2016-02-24 Smr发明技术有限公司 Managing nuclear reactor spent fuel rods

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5948934B2 (en) * 1981-05-30 1984-11-29 新日本製鐵株式会社 Manufacturing method of high magnetic flux density unidirectional electrical steel sheet
CN105359220A (en) * 2013-05-28 2016-02-24 Smr发明技术有限公司 Managing nuclear reactor spent fuel rods
CN104376882A (en) * 2014-11-11 2015-02-25 中科华核电技术研究院有限公司 Hot pipeline
CN104464851A (en) * 2014-12-19 2015-03-25 大连理工大学 Device and method for monitoring thermal fatigue prototype of loop high-temperature pipeline in nuclear power plant

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GB2581407B (en) 2022-12-07
GB201907946D0 (en) 2019-07-17

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