GB2581407B - Temperature measuring device in a nuclear reactor loop - Google Patents

Temperature measuring device in a nuclear reactor loop Download PDF

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Publication number
GB2581407B
GB2581407B GB1907946.6A GB201907946A GB2581407B GB 2581407 B GB2581407 B GB 2581407B GB 201907946 A GB201907946 A GB 201907946A GB 2581407 B GB2581407 B GB 2581407B
Authority
GB
United Kingdom
Prior art keywords
measuring device
temperature measuring
nuclear reactor
reactor loop
loop
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.)
Active
Application number
GB1907946.6A
Other versions
GB201907946D0 (en
GB2581407A (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
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

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
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 GB2581407A (en) 2020-08-19
GB2581407B true GB2581407B (en) 2022-12-07

Family

ID=67385888

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1907946.6A Active GB2581407B (en) 2018-07-03 2018-09-30 Temperature measuring device in a nuclear reactor loop

Country Status (1)

Country Link
GB (1) GB2581407B (en)

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

Also Published As

Publication number Publication date
GB201907946D0 (en) 2019-07-17
GB2581407A (en) 2020-08-19

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