CN107180656B - Heating device for simulating dead pipe section phenomenon of nuclear power station - Google Patents

Heating device for simulating dead pipe section phenomenon of nuclear power station Download PDF

Info

Publication number
CN107180656B
CN107180656B CN201710344763.1A CN201710344763A CN107180656B CN 107180656 B CN107180656 B CN 107180656B CN 201710344763 A CN201710344763 A CN 201710344763A CN 107180656 B CN107180656 B CN 107180656B
Authority
CN
China
Prior art keywords
heating body
heating
pipe section
nuclear power
simulating
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
CN201710344763.1A
Other languages
Chinese (zh)
Other versions
CN107180656A (en
Inventor
齐宇博
艾华宁
张伟
李剑波
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
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
Priority to CN201710344763.1A priority Critical patent/CN107180656B/en
Publication of CN107180656A publication Critical patent/CN107180656A/en
Application granted granted Critical
Publication of CN107180656B publication Critical patent/CN107180656B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/001Mechanical simulators
    • HELECTRICITY
    • H05ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05BELECTRIC HEATING; ELECTRIC LIGHT SOURCES NOT OTHERWISE PROVIDED FOR; CIRCUIT ARRANGEMENTS FOR ELECTRIC LIGHT SOURCES, IN GENERAL
    • H05B6/00Heating by electric, magnetic or electromagnetic fields
    • H05B6/02Induction heating
    • H05B6/06Control, e.g. of temperature, of power
    • HELECTRICITY
    • H05ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05BELECTRIC HEATING; ELECTRIC LIGHT SOURCES NOT OTHERWISE PROVIDED FOR; CIRCUIT ARRANGEMENTS FOR ELECTRIC LIGHT SOURCES, IN GENERAL
    • H05B6/00Heating by electric, magnetic or electromagnetic fields
    • H05B6/02Induction heating
    • H05B6/36Coil arrangements
    • H05B6/40Establishing desired heat distribution, e.g. to heat particular parts of workpieces
    • HELECTRICITY
    • H05ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05BELECTRIC HEATING; ELECTRIC LIGHT SOURCES NOT OTHERWISE PROVIDED FOR; CIRCUIT ARRANGEMENTS FOR ELECTRIC LIGHT SOURCES, IN GENERAL
    • H05B2206/00Aspects relating to heating by electric, magnetic, or electromagnetic fields covered by group H05B6/00
    • H05B2206/02Induction heating
    • 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

Landscapes

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

Abstract

The invention discloses a heating device for simulating the phenomenon of dead pipe sections of a nuclear power station, which comprises a simulated dead pipe section, a heating body, a heating coil and a plug bush, wherein the simulated dead pipe section is in a penetrating hollow structure, the cross section of the heating body is circular, the right end of the heating body is sealed and inserted into the simulated dead pipe section, the end face of the right end of the heating body is in an inclined check valve clack structure, the plug bush is in a hollow structure, the plug bush vertically penetrates into the simulated dead pipe section in a sealed manner and is inserted into the right end of the heating body, a probe of a thermal resistance thermometer is inserted into the plug bush in a sealed manner to collect the temperature of the heating body, the heating coil is arranged around the heating body, the heating coil is electrically connected with an external alternating current power supply, and the heating body generates induction current by virtue of an alternating magnetic field generated by the electrified heating coil so as to generate heat; the invention accurately simulates the environment of the phenomenon of dead pipe section, provides support for normal and safe operation of the actual nuclear power station, and has stronger practicability and popularization value.

Description

Heating device for simulating dead pipe section phenomenon of nuclear power station
Technical Field
The invention relates to a heating device, in particular to a heating device for simulating the dead pipe section phenomenon of a nuclear power station.
Background
RIS "dead pipe section": refers to the restricted space of the interface area of the RIS system (i.e., the safety injection system) and the RCP system (i.e., the reactor coolant system), and specifically refers to the conduit between the two check valves. During normal operation of the unit, the water stored in the pipeline is in a macroscopic static state, so the pipeline is called a dead pipe section.
"dead pipe section" phenomena and hazards: during normal operation of a nuclear power plant, the "dead pipe section" side is heated by RCP coolant (320 ℃), corrosion is observed on the valve flap wall surface of the side check valve, and the tightness is affected, and the corrosion phenomenon is called a "dead pipe section" phenomenon. The existence of this phenomenon directly threatens the reliability of the second safety barrier of the nuclear power plant.
In order to simulate the temperature, valve structure, etc. of the RCP side of the dead pipe section of a nuclear power plant, a product is required to have heating capability to cover the RCP temperature and to be consistent with the valve clack structure of the site of the nuclear power plant. The invention aims at the development of the actual demand, and the invention is a heating device with reasonable design, reliable process and stable performance.
Therefore, there is a need for a heating device that has both heating capability to cover the RCP system temperature and that simulates the dead leg phenomenon of a nuclear power plant consistent with the valve clack structure of the nuclear power plant site.
Disclosure of Invention
The invention aims to provide a heating device which has heating capacity to cover the temperature of an RCP system and can simulate the dead pipe section phenomenon of a nuclear power plant in accordance with the on-site valve clack structure of the nuclear power plant.
In order to achieve the above purpose, the invention provides a heating device for simulating the phenomenon of dead pipe sections of a nuclear power station, which is used for carrying out real-time measurement on the temperature by inserting an external thermal resistance temperature meter, and comprises a simulated dead pipe section, a heating body, a heating coil and a plug bush, wherein the simulated dead pipe section is in a through hollow structure, the cross section of the heating body is circular, the right end of the heating body is sealed and inserted into the simulated dead pipe section, the end face of the right end of the heating body is in an inclined check valve clack structure, the plug bush is in a hollow structure, the plug bush is vertically sealed and penetrates into the simulated dead pipe section and is inserted into the right end of the heating body, a probe of the thermal resistance temperature meter is sealed and inserted into the plug bush to collect the temperature of the heating body, the heating coil is arranged outside the heating body in a surrounding mode, the heating coil is electrically connected with an external alternating current power supply, and the heating body generates induction current by means of an alternating magnetic field generated by the heating coil when the heating coil is electrified.
Preferably, the heating body is a 15kw medium-frequency heat induction heater.
Preferably, the outer surface of the heating body is of an inclined structure.
Preferably, the plug bush comprises an insertion end, the insertion end is in a frustum structure, the insertion end vertically extends outwards to form a butt joint end, the insertion end vertically penetrates into the simulated dead pipe section in a sealing manner and is inserted into the right end of the heating body, and the butt joint end protrudes out of the heating body.
Preferably, the heating body is further provided with a measuring hole penetrating into the center.
Preferably, the measuring hole is opened from the end of the left end of the heating body to the right end.
Preferably, the measuring hole is located on the central axis of the heating body.
Preferably, the diameter of the measuring hole is 10mm, and the length of the measuring hole is 200mm.
Compared with the prior art, the invention heats the heating body by the electrified heating coil, realizes the function of effectively simulating the temperature of the RCP system, and simultaneously, the end face of the right end of the heating body inserted into the simulated dead pipe section is in an inclined check valve clack structure, so that the end face structure of the right end of the heating body is consistent with the check valve clack structure of the nuclear power plant site, thereby effectively simulating the check valve clack structure and physical properties of the dead pipe section of the nuclear power plant; the temperature of the heating body can be monitored in real time by the temperature of the heating body acquired by inserting the probe of the thermal resistance thermometer into the plug bush, so that the heating temperature of the heating body is regulated in real time by controlling the alternating current power supply, the heating body is always in the temperature range of the RCP system in the actual operation of the nuclear power plant, and the environment of the phenomenon of dead pipe section is accurately simulated; therefore, the heating device for simulating the dead pipe section phenomenon of the nuclear power plant, provided by the invention, not only has heating capacity to cover the temperature of the RCP system, but also can be consistent with the structure of the valve clack on the site of the nuclear power plant, accurately simulates the environment of the dead pipe section phenomenon, provides support for normal and safe operation of the actual nuclear power plant, and has stronger practicability and popularization value.
Drawings
Fig. 1 is a schematic structural view of a heating device for simulating the dead pipe section phenomenon of a nuclear power plant according to the present invention.
Fig. 2 is a sectional view of the heating apparatus for simulating the dead pipe section phenomenon of the nuclear power plant according to the present invention with the heating coil removed.
Detailed Description
Embodiments of the present invention will now be described with reference to the drawings, wherein like reference numerals represent like elements throughout.
As shown in fig. 1 and 2, the heating device 100 for simulating the dead pipe section phenomenon of a nuclear power station according to the present invention inserts an external thermal resistance thermometer to perform real-time measurement of temperature, the heating device 100 for simulating the dead pipe section phenomenon of a nuclear power station includes a simulated dead pipe section 1, a heating body 2, a heating coil 3 and a plug bush 4, the simulated dead pipe section 4 has a through hollow structure, the material, the size and the specification of the simulated dead pipe section 4 are the same as those of the dead pipe section on site of the nuclear power station, the cross section of the heating body 2 has a circular shape, the right end 21 of the heating body 2 is inserted into the simulated dead pipe section 1 in a sealing manner, specifically, the right end 21 of the heating body 2 is inserted into the simulated dead pipe section 1 and then welded to seal the two; the end face 22 of the right end 21 of the heating body 2 is of an inclined check valve clack structure, so that the end face 22 of the right end of the heating body 2 is identical to the check valve clack structure of a check valve in the nuclear power station site; the plug bush 4 is of a hollow structure 41, the plug bush 4 vertically penetrates into the simulated dead pipe section 1 in a sealing manner and is inserted into the right end 21 of the heating body 2, specifically, the right end 21 of the heating body 2 is provided with an inserting hole 23 corresponding to the plug bush 2, the plug bush 4 vertically penetrates into the cylinder wall of the simulated dead pipe section 1 and is correspondingly inserted into the inserting hole 23 of the heating body 2, and the plug bush 4 and the cylinder wall of the simulated dead pipe section 1 are fixed in a sealing manner by a welding mode of a pile welding seam; the probe of the thermal resistance thermometer is sealed and inserted into the hollow structure 41 of the plug bush 4 to collect the temperature of the heating body 2, the heating coil 3 is arranged outside the heating body 2 in a surrounding way, the heating coil 3 is electrically connected with an external alternating current power supply, the heating body 2 generates induction current by means of an alternating magnetic field generated by the electrified heating coil 3 so as to generate heat, specifically, the heating coil 3 generates an alternating magnetic field under the action of the alternating current power supply, the alternating magnetic field acts on the fixed heating body 2, the heating body 2 generates induction current, the induction current acts on the conductive heating body 2 to enable the heating body 2 to generate heat (namely, electric energy is converted into heat energy), the heating purpose is achieved, and the temperature of an RCP system is simulated. The heating body 2 effectively simulates the temperature of an RCP system, and simultaneously, the end face 22 of the right end 21 of the heating body 2 inserted into the simulated dead pipe section 1 is in an inclined check valve clack structure, so that the end face 22 of the right end 21 of the heating body 2 is consistent with the check valve clack structure of a nuclear power plant site, and further, the structure and physical properties of the check valve clack of the dead pipe section of the nuclear power plant are effectively simulated; the temperature of the heating body 2 can be monitored in real time by the temperature of the heating body acquired by inserting the probe of the thermal resistance thermometer into the plug bush, so that the heating temperature of the heating body 3 is regulated in real time by controlling the alternating current power supply, the heating body 2 is always in the temperature range of the RCP system in the actual operation of the nuclear power plant, and the environment of the phenomenon of dead pipe section is accurately simulated. The following further describes in detail the heating device 100 for simulating the dead pipe section phenomenon of a nuclear power plant according to the present invention with reference to fig. 1 and 2:
preferably, the heating body 2 is a 15kw medium frequency induction heater.
As shown in fig. 1 and 2, preferably, the outer surface of the heating body 2 has an inclined structure; the outer surface of the heating body 2 is of an inclined structure, so that the structure of the heating body is consistent with the structure of a check valve on the site of the nuclear power station, and further, the structure of a check valve clack of the check valve can be further and more accurately simulated.
As shown in fig. 1 and 2, preferably, the plug bush 4 of the heating device 100 for simulating the dead pipe section phenomenon of the nuclear power station of the present invention comprises an insertion end 42, the insertion end 42 is in a frustum structure, the insertion end 42 extends vertically outwards to form a butt joint end 43, the insertion end 42 penetrates into the simulated dead pipe section 1 in a vertical sealing manner and is inserted into the right end 21 of the heating body 2, and the butt joint end 43 protrudes out of the heating body 2; specifically, the insertion end 42 is inserted into the insertion hole 23 of the heating body 2, and the insertion end 42 and the wall of the simulated dead pipe section 1 are sealed, welded and fixed by welding the bead weld 24.
As shown in fig. 2, preferably, the heating body 2 is further provided with a measuring hole 25 penetrating into the center; the external temperature measuring device is inserted into the measuring hole 25, so that the heating temperature of the heating body 2 can be effectively measured uniformly, the heating effect of the heating body 2 is further controlled, and the RCP system temperature is more accurately simulated. Specifically, in order to further enable the temperature measuring device to go deep into the measuring hole 25 to accurately measure the heating temperature of the heating body, the measuring hole 25 is opened from the end face 26 of the left end of the heating body 2 to the right end 21; more specifically, the measurement hole 25 is located on the central axis of the heating body 2.
Preferably, the diameter of the measuring hole 25 is 10mm, and the length of the measuring hole 25 is 200mm.
In addition, the welding mode according to the embodiment of the invention meets the RCC-M, GB150 standard and has enough mechanical strength.
As shown in fig. 1 and 2, the heating body 2 is heated by the heating coil 3 which is electrified, so that the function of effectively simulating the temperature of an RCP system of the heating body 2 is realized, and meanwhile, the end face 22 of the right end 21 of the heating body 2 inserted into the simulated dead pipe section 1 is in an inclined check valve clack structure, so that the end face 22 of the right end 21 of the heating body 2 is consistent with the check valve clack structure of a nuclear power plant site, and further, the structure and physical properties of the check valve clack structure of the dead pipe section of the nuclear power plant are effectively simulated; the temperature of the heating body 2 collected by the probe insertion sleeve 4 of the thermal resistance thermometer can be monitored in real time, so that the heating temperature of the heating body 3 is regulated in real time by controlling an alternating power supply, the heating body 3 is always in the temperature range of an RCP system in the actual operation of a nuclear power plant, and the environment of a dead pipe section phenomenon is accurately simulated; therefore, the heating device 100 for simulating the dead pipe section phenomenon of the nuclear power plant not only has heating capacity to cover the temperature of the RCP system, but also can be consistent with the on-site valve clack structure of the nuclear power plant, accurately simulates the environment of the dead pipe section phenomenon, provides support for normal and safe operation of the actual nuclear power plant, and has strong practicability and popularization value.
In addition, the specific structure and the working principle of the phenomenon of the dead pipe section of the nuclear power station according to the present invention are well known to those skilled in the art, and will not be described in detail herein.
The foregoing description of the preferred embodiments of the present invention is not intended to limit the scope of the claims, which follow, as defined in the claims.

Claims (8)

1. A heating device for simulating the dead pipe section phenomenon of a nuclear power station inserts an external thermal resistance thermometer to measure the temperature in real time, which is characterized in that: the heating device for simulating the phenomenon of the dead pipe section of the nuclear power station comprises a simulated dead pipe section, a heating body, a heating coil and a plug bush, wherein the simulated dead pipe section is of a penetrating hollow structure, the cross section of the heating body is circular, the right end of the heating body is inserted into the simulated dead pipe section in a sealing manner, the end face of the right end of the heating body is of an inclined check valve clack structure, the plug bush is of a hollow structure, the plug bush vertically penetrates into the simulated dead pipe section in a sealing manner and is inserted into the right end of the heating body, a probe of a thermal resistance temperature meter is inserted into the plug bush in a sealing manner to collect the temperature of the heating body, the heating coil surrounds the heating body, the heating coil is electrically connected with an external alternating current power supply, and the heating body generates induction current and further generates heat by virtue of an alternating magnetic field generated by the heating coil which is electrified.
2. A heating device for simulating dead leg phenomenon in nuclear power plants as defined in claim 1, wherein: the heating body is a 15kw medium-frequency heat induction heater.
3. A heating device for simulating dead leg phenomenon in nuclear power plants as defined in claim 1, wherein: the outer surface of the heating body is of an inclined structure.
4. A heating device for simulating dead leg phenomenon in nuclear power plants as defined in claim 1, wherein: the plug bush comprises an insertion end, the insertion end is of a frustum structure, the insertion end vertically extends outwards to form a butt joint end, the insertion end vertically penetrates into the simulated dead pipe section in a sealing mode and is inserted into the right end of the heating body, and the butt joint end protrudes out of the heating body.
5. A heating device for simulating dead leg phenomenon in nuclear power plants as defined in claim 1, wherein: the heating body is also provided with a measuring hole penetrating into the center.
6. A heating apparatus for simulating dead leg phenomenon in nuclear power plants as set forth in claim 5, wherein: the measuring hole is formed from the end face of the left end of the heating body to the right end.
7. A heating apparatus for simulating dead leg phenomenon in nuclear power plants as set forth in claim 6, wherein: the measuring hole is positioned on the central axis of the heating body.
8. A heating apparatus for simulating dead leg phenomenon in nuclear power plants as set forth in claim 7, wherein: the diameter of the measuring hole is 10mm, and the length of the measuring hole is 200mm.
CN201710344763.1A 2017-05-16 2017-05-16 Heating device for simulating dead pipe section phenomenon of nuclear power station Active CN107180656B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201710344763.1A CN107180656B (en) 2017-05-16 2017-05-16 Heating device for simulating dead pipe section phenomenon of nuclear power station

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201710344763.1A CN107180656B (en) 2017-05-16 2017-05-16 Heating device for simulating dead pipe section phenomenon of nuclear power station

Publications (2)

Publication Number Publication Date
CN107180656A CN107180656A (en) 2017-09-19
CN107180656B true CN107180656B (en) 2024-04-09

Family

ID=59832616

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201710344763.1A Active CN107180656B (en) 2017-05-16 2017-05-16 Heating device for simulating dead pipe section phenomenon of nuclear power station

Country Status (1)

Country Link
CN (1) CN107180656B (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111128416A (en) * 2019-12-31 2020-05-08 西安交通大学 Visual thermal hydraulic experiment device and method for dead pipe section of nuclear power station

Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA1086925A (en) * 1978-08-22 1980-10-07 Frank Stern Direct heater with axially varying power distribution
GB8314030D0 (en) * 1983-05-20 1983-06-29 Atomic Energy Authority Uk Heat flux simulators
SE8502645D0 (en) * 1984-05-31 1985-05-29 Daiichi Koshuha Kogyo Kk HEATING PROCEDURE AND APPLIANCES TO REDUCE CURRENT VOLTAGE IN A WELD JOINT BETWEEN HEAD AND BRANCH
US5361284A (en) * 1993-03-04 1994-11-01 Westinghouse Electric Corporation Tube corrosion accelerator
FR2891908A1 (en) * 2005-10-12 2007-04-13 Agence Spatiale Europeenne DEVICE AND METHOD FOR PERFORMING TESTS ON MATERIALS
CN201314459Y (en) * 2008-11-28 2009-09-23 中广核工程有限公司 Structure for improving internal pressure of still pipe segment
KR20100089330A (en) * 2009-02-03 2010-08-12 한국원자력연구원 A nuclear fuel sheath for creating a copy crud, method for manufacturing thereof and apparatus for creating a copy crud
CN201975092U (en) * 2011-01-21 2011-09-14 中广核工程有限公司 Pipeline in nuclear power plant for connecting residual heat removal system and loop
CN103545000A (en) * 2013-10-21 2014-01-29 中国核动力研究设计院 Secondary-side passive residual heat discharging heat exchanger simulation device and method
JP2015056224A (en) * 2013-09-10 2015-03-23 中部電力株式会社 Induction heating apparatus
CN206789312U (en) * 2017-05-16 2017-12-22 中广核研究院有限公司 Simulate the heater of the dead pipeline section phenomenon of nuclear power station

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100909118B1 (en) * 2008-10-09 2009-07-23 한국항공대학교산학협력단 Apparatus for forming a stress corrosion crack
FR2975527B1 (en) * 2011-05-18 2013-07-05 Commissariat Energie Atomique DEVICE FOR ELECTRICALLY HEATING A LIQUID, ITS PRODUCTION METHOD AND APPLICATION TO THE ELECTRICAL SIMULATION OF NUCLEAR FUEL PENCILS

Patent Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA1086925A (en) * 1978-08-22 1980-10-07 Frank Stern Direct heater with axially varying power distribution
GB8314030D0 (en) * 1983-05-20 1983-06-29 Atomic Energy Authority Uk Heat flux simulators
SE8502645D0 (en) * 1984-05-31 1985-05-29 Daiichi Koshuha Kogyo Kk HEATING PROCEDURE AND APPLIANCES TO REDUCE CURRENT VOLTAGE IN A WELD JOINT BETWEEN HEAD AND BRANCH
US5361284A (en) * 1993-03-04 1994-11-01 Westinghouse Electric Corporation Tube corrosion accelerator
FR2891908A1 (en) * 2005-10-12 2007-04-13 Agence Spatiale Europeenne DEVICE AND METHOD FOR PERFORMING TESTS ON MATERIALS
CN201314459Y (en) * 2008-11-28 2009-09-23 中广核工程有限公司 Structure for improving internal pressure of still pipe segment
KR20100089330A (en) * 2009-02-03 2010-08-12 한국원자력연구원 A nuclear fuel sheath for creating a copy crud, method for manufacturing thereof and apparatus for creating a copy crud
CN201975092U (en) * 2011-01-21 2011-09-14 中广核工程有限公司 Pipeline in nuclear power plant for connecting residual heat removal system and loop
JP2015056224A (en) * 2013-09-10 2015-03-23 中部電力株式会社 Induction heating apparatus
CN103545000A (en) * 2013-10-21 2014-01-29 中国核动力研究设计院 Secondary-side passive residual heat discharging heat exchanger simulation device and method
CN206789312U (en) * 2017-05-16 2017-12-22 中广核研究院有限公司 Simulate the heater of the dead pipeline section phenomenon of nuclear power station

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
THERMAL FATIGUE SCREENING CRITERIA FOR IDENTIFYING SUSCEPTIBLE PIPING COMPONENTS IN CANDU® STATIONS;C Schefski et.al.;AFAL CW-33000-CONF-002;1-8 *
高亚甫等.压水堆核电站"死管段"现象数值模拟分析.第15 届全国反应堆结构力学会议论文集.2008,173-179. *

Also Published As

Publication number Publication date
CN107180656A (en) 2017-09-19

Similar Documents

Publication Publication Date Title
CN106016710B (en) A kind of electric heater of intelligent overheating detection
CN107367058B (en) A kind of electric heater of temperature control hot water temperature
CN104950039A (en) Ferromagnetic pipeline quantitative lossless evaluating method based on nonlinear magnetic saturation pulsed eddy current
CN104464851B (en) A kind of monitoring method for one loop of nuclear power station high-temperature pipe heat exhaustion prototype
CN104078087B (en) A kind of cluster testpieces of simulating Supercritical-Pressure Light Water Cooled Reactor fuel element
CN107166742B (en) A kind of electric heater automatically controlling leakage
CN106952669B (en) Stagnation pressure external container cooling test rack in a kind of fusant heap
CN104614310B (en) A kind of high temperature pressure corrosion electro-chemical measuring apparatus and measuring method
CN103106935A (en) Apparatus and method for detecting position of annulus spacer between concentric tubes
CN201622133U (en) Magnetic force surface temperature sensor
CN105588774A (en) Model test system for materials of surrounding rock and lining structures of high-ground-temperature diversion tunnel
CN105466837A (en) Test device for submarine cable water permeability test and submarine cable water permeability test method
CN107180656B (en) Heating device for simulating dead pipe section phenomenon of nuclear power station
CN102353628A (en) Polarization testing probe and testing method for cathodic protection of underground steel pipelines
CN107945895A (en) A kind of non-homogeneous electrically heated nuclear fuel simulation rod
CN112304790A (en) Fatigue test method for heat supply directly-buried pipeline
CN104357644A (en) Circular seam heat treatment system of nuclear power vapor generator and application of heat treatment system
CN203979668U (en) A kind of prefabricated thermal insulation type is crossed wall coil
CN105258764A (en) Method for real-time continuous liquid level measurement
CN206479579U (en) A kind of axle sample resistivity experimental provision of temperature control three
CN109211969B (en) A kind of triaxial ellipsoid shape fusion pool heat transfer characteristic measurement experiment device
CN206789312U (en) Simulate the heater of the dead pipeline section phenomenon of nuclear power station
CN111128416A (en) Visual thermal hydraulic experiment device and method for dead pipe section of nuclear power station
CN207425373U (en) A kind of non-homogeneous electrically heated nuclear fuel simulation stick
CN206672646U (en) Stagnation pressure external container cooling test stand in a kind of fused mass heap

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant