• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
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    • 专利摘要:
    A multithermocouple core instrument set and system and method for monitoring the internal state of a nuclear reactor after a severe accident using the core instrument assembly. In accordance with one embodiment of the present invention, a multithermocouple core instrument assembly (10 ') includes a signal compensation detector, thermocouples (121 to 125), and a plurality of neutron detectors disposed between a central pipe. having a circular section and an outer protective pipe, and the thermocouples (121 to 125) have temperature measuring points at different heights.
    公开号:FR3029344A1
    申请号:FR1561514
    申请日:2015-11-27
    公开日:2016-06-03
    发明作者:Song Hae Ye；Yeong Cheol Shin；Soo Lee Iii；Kwang Dae Lee；Hong Ki Jung；Hee Taek Lim；Yong Sik Kim；Kye Hyeon Ryu；Myung Eun Chae；Sung Jin Kim
    申请人:Woojin Osk Corp；Korea Hydro and Nuclear Power Co Ltd；
    IPC主号:
    专利说明:

    [0001] TECHNICAL FIELD The present invention relates to a multithermocouple instrument assembly in the heart, which assists, and assists the system and method for monitoring the internal state of a nuclear reactor after a severe accident using it. BACKGROUND OF THE INVENTION the diagnosis of the internal state of a nuclear reactor, specifically by providing temperature information at different heights within the nuclear reactor using a plurality of thermocouples having temperature measurement points at different heights, and system and method for monitoring the internal state of a nuclear reactor after a serious accident using the core instrument assembly. Related Art Disclosure A plurality, for example, 61, of core instrument assemblies fixedly installed within a nuclear reactor serves as a support for a neutron flux within the nuclear reactor to be accurately measured by three dimensions and their output distribution can be monitored. A core element of the core instrument array is a self-powered neutron detector including a transmitter for absorbing neutrons and emitting a signal current. A conventional self-powered neutron detector using rhodium (Rh) is governed by the principle of the neutron capture reaction of a rhodium-emitting substance. When neutrons incident on the rhodium are captured, they emit high energy electrons with sufficient energy for the neutrons to deviate from the transmitter while experiencing beta decay. The emitted electrons are collected by a collector via an aluminum oxide insulator (A1203), and positive charges are generated at a conductor attached to the emitter. The positive charges generated generate an electric current in proportion to the neutron absorption ratio of the transmitter. The neutron detector is divided into a rhodium detector (Rh), a vanadium detector (V), a cobalt detector (Co) and a platinum detector (Pt) depending on the materials of the transmitter. Figure 1 is a front view of a conventional core instrument set. As illustrated in FIG. 1, the conventional core instrument assembly 10 includes a measurement unit 20, a sealing fitting 30, a flexible conduit 40, and a connector. The measuring unit 20 surrounds an outer protection pipe 25, and a bullet tip 26 is connected to one end of the measuring unit 20. The measuring unit 20 is inserted into a nuclear reactor via a guide tube (not shown), and has a length of about 36 m. FIG. 2 is a longitudinal sectional view taken along the line AA of FIG. 1. As illustrated in FIG. 2, the measuring unit 20 of the conventional core instrument assembly 10 is configured to include a central pipe 21, a thermocouple 22, a signal compensation detector 24, an external protective pipe 25 and neutron detectors 27. In the aforementioned configuration, the central pipe 21 penetrates the inside of the measuring unit 20 in one direction of the length. The central pipe 21 has a hollow tube shape to have the same diameter as a guide tube, and the length of the central pipe 21 has been approximately standardized. The thermocouple 22 includes a pair of cables having a circular cross-section, namely a chromel wire 22a and the alumel wire 22b, and is used to measure a temperature of a coolant within a nuclear reactor. A type K thermocouple is mainly used as a thermocouple 22. The neutron detector 27 also has a cable shape having a circular section. A total of five (strands of) neutron detectors 27 are used to measure a neutron flux within the nuclear reactor. Only one (strand of) signal compensation detector 24 is implemented in the form of a cable having a circular section and used for measuring a signal (background noise). In this case, each of the neutron detectors 27, 25 of the thermocouple 22 and the signal compensation detector 24 (hereinafter collectively referred to as the "detector") has approximately the same length and diameter. The measurement unit 20 further includes a total of 8 (strands of) fill cables 23 for filling voids to prevent fluctuation of each detector due to a difference in diameter between the central pipe 21 and the detector and to arrange each neutron detector 27 at a desired location (or angle) when the neutron detector 27, the thermocouple 22 and the signal compensation detector 24 are arranged to surround the central pipe 21 in the space between the pipe 21 and the outer protective tube 25. In accordance with the above-mentioned conventional core instrument assembly, there is the problem that the use of the relatively expensive core instrument assembly is small because all eight cables Filling is used only to prevent the fluctuation of each detector and maintain the distance between the detectors. Referring to FIG. 3, the conventional nuclear reactor core instrument assembly is inserted into a nuclear reactor, and monitors a neutron flux within a reactor core and a temperature at the top end of the core. reactor. The core instrument assembly 10 is inserted into a nuclear reactor 1001 via a guide tube 1005, and determines a temperature (650 degrees) at the outlet at the top of the reactor core as a condition of entry into the reactor. a serious accident using a single type K thermocouple disposed at the end of the core instrument assembly 10. Namely, in the conventional core instrument assembly 10, if a serious accident occurs, information about a reactor core temperature is totally lost when a reactor core peak 1002a is seriously damaged because only a reactor core top temperature 1002a is measured. Moreover, it is impossible to measure the cooling, overheating, oxidation and serious damage state of the entire reactor core (including the middle and bottom of the reactor core), the reactor core rearrangement. melted in the lower cavity 1001a and the inner lid 100b of a nuclear reactor container on the lower side of the reactor core, and a direct temperature distribution for monitoring the deflection state of the nuclear reactor container. As a result, there is the problem that it is difficult to verify the internal state of the nuclear reactor container to optimally manage a serious accident and establish a strategy for managing an accident, such as cooling and cooling. elimination of hydrogen. Prior Art Document Patent Document Publication of Korean Patent Application No. 102014-0 010 501 entitled "Core Instrument Set for Improving the Sensitivity of Neutron Flux Detection". SUMMARY OF THE INVENTION An object of the present invention is to provide a core multithermocouple instrument assembly which assists in diagnosing the internal state of a nuclear reactor more precisely by providing temperature information at different heights within the reactor. nuclear reactor using a plurality of thermocouples having temperature measurement points at different heights. Another object of the present invention is to provide a core multithermocouple instrument assembly, which is capable of maximizing the use of an apparatus by providing temperature information at different heights within a nuclear reactor using a plurality of Thermocouples having temperature measurement points at different heights instead of filling cables. Yet another object of the present invention is to provide a system and method for monitoring the internal state of a nuclear reactor after a severe accident, which are capable of monitoring the cooling and overheating state of a core of reactor in each part of a nuclear reactor core and the water level of a nuclear reactor container when a serious accident occurs. Yet another object of the present invention is to provide a system and method for monitoring the internal state of a nuclear reactor after a severe accident, which are capable of monitoring an oxidation state generated by a hydration reaction between a reactor core in each part of a nuclear reactor core and steam when a serious accident is generated and a state of serious damage in which the normal geometry of the reactor core can not be preserved.
    [0002] Yet another object of the present invention is to provide a system and method for monitoring the internal state of a nuclear reactor after a severe accident, which are capable of monitoring the amount of hydrogen to which a nuclear reactor can explode in based on the amount of oxidation of each part of a reactor core when a severe accident occurs. Yet another object of the present invention is to provide a system and method for monitoring the internal state of a nuclear reactor after a severe accident, which are capable of monitoring the state in which a molten reactor core has been repositioned in the lower cavity of a nuclear reactor container over time after a serious accident has occurred and the state in which a molten reactor core can deviate from a lower lid. An object of the present invention is achieved by a core multithermocouple instrument assembly, wherein the core instrument array includes a signal compensation detector, thermocouples, and a plurality of neutron detectors disposed between a central pipe having a circular cross section. and an external protective hose, and the thermocouples have temperature measurement points at different heights. The signal compensation detector is one in number, there are five neutron detectors, and there are two to five thermocouples. If four thermocouples or less are installed, the space in which the thermocouple is not installed may be filled with filler cables. The thermocouple or the charging cables and the neutron detector can be arranged alternately. An empty space can be filled with fill cables if the void space is formed above the thermocouple. Each of the thermocouples can be formed by connecting adjacent wires made of different materials. Yarns made of different materials may include chromel yarn and alumel yarn. Another object of the present invention can be achieved by a system for monitoring the internal state of a nuclear reactor after a severe accident, including a core instrument set inserted into the nuclear reactor and configured to measure neutrons and a temperature. within the nuclear reactor; and a diagnostic unit configured to determine a state of the nuclear reactor based on the temperature measured by the core instrument set, wherein the core instrument set comprises two or more thermocouples, and two core instrument sets or more are inserted and arranged in the nuclear reactor at a specific interval. The two or more thermocouples may have different heights in one direction of length. The diagnostic unit can determine at least one of: the damage or not of a reactor core, the location of a damaged reactor core, a quantity of hydrogen generated in the nuclear reactor, a state in which a molten reactor core has been redisposed, and a moment when a molten reactor core enters the nuclear reactor based on a temperature measured by the two or more thermocouples. At least one of: damage to the reactor core, the location of the damaged reactor core and the amount of hydrogen generated in the nuclear reactor can be determined based on oxidation of core materials. reactor and a time during which the materials are exposed to a high temperature. At least one of the state in which the molten reactor core has been redisposed and the moment the molten reactor core enters the nuclear reactor can be determined based on a lower cavity temperature under the reactor. nuclear or a lower cover. An object of the invention is achieved by a method of monitoring the internal state of a nuclear reactor after a serious accident using a core instrument assembly, the method including the steps of: (A) providing two thermocouples or more in the whole instrument in heart; (B) providing two or more thermocouples at different heights in a lengthwise direction; (C) inserting two or more core instrument sets into the nuclear reactor; and (D) measuring temperatures at different heights within the nuclear reactor through the thermocouples.
    [0003] The method may further include a step of (E) determining at least one of: damage to a reactor core, the location of a damaged reactor core, the amount of hydrogen generated in the nuclear reactor, a state in which a molten reactor core has been rearranged, and a moment when a molten reactor core enters the nuclear reactor based on a temperature in the nuclear reactor measured at step (D). At least one of: damage to the reactor core, the location of the damaged reactor core and the amount of hydrogen generated in the nuclear reactor can be determined based on the oxidation of the reactor materials. reactor core and a moment during which the materials are exposed to a high temperature. At least one of the state in which the molten reactor core has been rearranged and the moment the molten reactor core enters the nuclear reactor can be determined based on a lower cavity temperature under the reactor. nuclear or a lower cover. BRIEF DESCRIPTION OF THE DRAWINGS Fig. 1 is a front view of a conventional core instrument set; Figure 2 is a longitudinal sectional view taken along the line A-A of Figure 1; Fig. 3 is a longitudinal sectional view illustrating that a conventional core instrument assembly has been installed in a reactor core; Fig. 4 is a front view of a multithermocouple core instrument assembly in accordance with an embodiment of the present invention; Figure 5 is a longitudinal sectional view taken along the line A-A of Figure 4; Fig. 6 is a structural diagram illustrating the state in which the interior of the multithermocouple core instrument assembly in accordance with an embodiment of the present invention has been deployed on a plane; Figures 7 to 9 illustrate a system for monitoring the internal state of a nuclear reactor after a severe accident in the nuclear reactor in accordance with an embodiment of the present invention; and Fig. 10 illustrates a system for monitoring the internal state of a nuclear reactor after a severe accident in the nuclear reactor in accordance with another embodiment of the present invention. DETAILED DESCRIPTION OF THE EMBODIMENTS Hereinafter, embodiments of a core multithermocouple instrument assembly according to the present invention will be described in detail with reference to the accompanying drawings. Fig. 4 is a front view of a core multithermocouple instrument assembly in accordance with an embodiment of the present invention. As illustrated in FIG. 4, the core instrument assembly 10 'including a multithermocouple in accordance with an embodiment of the present invention includes a measurement unit 100, a sealing fitting 30, a flexible conduit 40, and a connector. The measuring unit 100 is surrounded by an external protective hose 25. A bullet tip 26 is connected to one end of the measuring unit 100.
    [0004] The measurement unit 100 is inserted into a nuclear reactor via a guide tube (not shown) and has a length of about 36 m. FIG. 5 is a longitudinal sectional view taken along the line AA of FIG. 4. FIG. 5 is a longitudinal sectional view of the lower part of the measurement unit 100 in the state in which the unit 100 has been installed at a portion adjacent to the sealing connection 30 of the measuring unit 100, namely within the nuclear reactor. As illustrated in FIG. 5, the measurement unit 100 of the core instrument set according to one embodiment of the present invention is substantially configured to include a central pipe 110, a thermocouple 121, a compensation detector signal 140, an external protective pipe 150 and neutron detectors 170. In the above-mentioned configuration, the central pipe 110 penetrates the inside of the measuring unit 100 in the direction of the length of the measuring unit 30. 100. The central pipe 110 is configured as a hollow tube having a diameter to prevent fluctuation from being generated within a guide tube (not shown) because the central pipe 110 is inserted into the nuclear reactor through the guide tube. The length of the central pipe 110 has been approximately standardized. The neutron detector 170 is also implemented in the form of a cable having a circular section. A total of five (strands of) neutron detectors 170 are used to measure a neutron flux within the nuclear reactor. A single (strand of) signal compensation detector 140 is also implemented as a cable having a circular section and used to measure a signal (or background noise). The core multithermocouple instrument assembly in accordance with one embodiment of the present invention may further include additional thermocouples 122 to 125 in addition to the thermocouple 121 which is used to measure a coolant temperature within a reactor. nuclear power
    [0005] The additional thermocouples 122 to 125 may include a maximum of 4 thermocouples since they may be included in place of a total of 8 fill cables included in a conventional core instrument set. In this case, in order to detect temperatures at different points (or different heights) within the nuclear reactor, the thermocouples 121 to 125 may have temperature measurement points at different heights. In addition, the chromite wire 121a and the alumel wire 121b of each of the thermocouples 121-125 need to be installed adjacent so that a contact point can be formed at the ends of the chromel wire and the wire. alumel wire. The neutron detector 170 may be disposed between the thermocouples 121 to 125 so that the influence of an electric field generated by the thermocouples 121 to 125 is minimized and the neutron detectors 170 are arranged at equal intervals. Each of the thermocouples 121-125 includes a pair of cables having a circular cross-section, namely, the chromel wire 121a and the alumel wire 121b. The thermocouple can be implemented using a type K thermocouple capable of detecting a temperature of 1260 ° C. Fig. 6 is a structural diagram illustrating the state in which the interior of the core multithermocouple instrument assembly in accordance with an embodiment of the present invention has been deployed on a plane. As illustrated in FIG. 6, the core multithermocouple instrument assembly in accordance with one embodiment of the present invention may include all five thermocouples 121 to 125 having temperature measurement points formed in the respective sections of the invention. a nuclear reactor in the state in which the interior of the nuclear reactor has been divided into five equal parts. In this case, for example, the thermocouple 121 having the temperature measurement point formed near the top of the measurement unit 100 has no problem of fluctuation because the neutron detector 170 adjacent the thermocouple 121 or the detector 140 signal compensation have almost the same length. In contrast, in each of the thermocouples 122 to 125 having the temperature measurement points formed at locations lower than the location of the temperature measuring point of the thermocouple 121, there may be the problem that the neutron detector 170 or the signal compensation detector 140 undergoes a fluctuation or is bent through a void space because the void space is formed above each of the thermocouples 122 to 125. In order to prevent such a problem, the voids formed above above thermocouples 122 to 125 having low temperature measurement points may be filled with respective charging cables 131 to 134. As a result, the charging cables 131 to 134 may have different lengths, and a total length of the thermocouples 122 to 125 and the charging cables 131 to 134 may be the same as the length of the neutron detector 170 or the compensation detector signal 140.
    [0006] Although an embodiment of the core multithermocouple instrument assembly according to the present invention has been described above, the embodiment is only illustrative, and the core instrument set in accordance with a Embodiment of the present invention may be modified and varied in a variety of ways without departing from the category of the technical mind. For example, the number of thermocouples 121 to 125 may be two to four, not five. In this case, an empty space from which the thermocouple has been removed can be filled with conventional fill cables.
    [0007] The interval between the temperature measuring points of the thermocouples 121 to 125 and the length of the thermocouples 121 to 125 can also be correctly changed.
    [0008] If a total of five thermocouples is included, two or three of the thermocouples may have temperature measurement points of the same height to ensure reliable measurement results. In addition, the top spaces of all thermocouples may be empty. In this case, all the empty spaces can be filled by the filling cables. The thermocouple may include a type of thermocouple other than the type K. A system and method for monitoring the internal state of a nuclear reactor after a severe accident in accordance with embodiments of the present invention are described herein by FIGS. 7 to 9 illustrate a system 1000 for monitoring the internal state of a nuclear reactor after a serious accident in the nuclear reactor in accordance with an embodiment of the present invention. Referring to FIGS. 7 to 9, the system for monitoring the internal state of a nuclear reactor after a severe accident in accordance with an embodiment of the present invention may include the core instrument sets 10 'and a unit The core instrument assembly 10 'in accordance with one embodiment of the present invention is inserted into a nuclear reactor 1001, and measures neutrons and a temperature within the nuclear reactor 1001. In this case, the core instrument assembly 10 'includes two or more thermocouples (e.g., a first thermocouple, a second thermocouple, and a fifth thermocouple). In addition, two thermocouples 121 to 125 or more have different heights in the thermocouple length direction and can measure mid and / or bottom temperatures in addition to the top of a 1002 reactor core. at least two core instrument sets 10 'in accordance with one embodiment of the present invention are inserted into the nuclear reactor 1001 and can be disposed in the reactor core 1002 at a constant interval. Referring to FIGS. 7 to 9, each of the core instrument sets 10 'may be inserted into the nuclear reactor through a guide tube 1005 installed at a lower portion of the nuclear reactor 1001. The diagnostic unit 1200 in accordance with one embodiment of the present invention can determine the state of the nuclear reactor 1001 based on temperatures measured by the thermocouple 121-125 of the core instrument assembly 10 '. Referring to Fig. 7, a separate transmission cable 1300 connected to the end of the core instrument assembly 10 'is installed for transferring temperature information from the core instrument assembly 10' to the core instrument assembly 10 '. diagnostic unit 1200 via the transmission cable 1300. The diagnostic unit 1200 can determine at least one of the cooling, overheating, oxidation, serious damage and melting state (e.g., the location and degree of melt) of the reactor core 1002, the state of rearrangement of the molten reactor core in the lower cavity 1001a of a nuclear reactor container, and a hazard for which a molten reactor core can deviate from the lower lid 100lb of the nuclear reactor container. The system 1000 for monitoring the internal state of a nuclear reactor after a serious accident in accordance with an embodiment of the present invention may include the two core instrument sets 10 'or more. The core instrument sets 10 'in accordance with one embodiment of the present invention may be installed in the reactor core 1002. In the system 1000 for monitoring the internal state of a nuclear reactor after a serious accident in In accordance with one embodiment of the present invention, all core instrument sets 10 'can be inserted into the nuclear reactor 1001. Referring to FIG. 7, the vertex thermocouple 121 of the thermocouples included in each Core Instrument Sets 10 'measures the temperature of a reactor core 1002a as in a conventional core instrument set. In addition, the lower thermocouple 125 of the thermocouples included in the core instrument assembly 10 'can be installed in the lower cavity 1001a of the nuclear reactor container under the reactor core 1002, and can detect the temperature of the lower cavity 1001a. nuclear reactor container. In another embodiment, referring to FIG. 8, the vertex thermocouple 121 of the thermocouples included in each of the core instrument sets 10 'measures the temperature of the reactor core 1002a as in a conventional core instrument set. . In addition, the lower thermocouple 125 may be installed in the lower cover 100lb of the nuclear reactor container placed under the reactor core 1002, and can measure the temperature of the lower cover 100lb of the nuclear reactor container. Alternatively, with reference to Fig. 9, each of the first and second core instrument sets 10'a and 10'b which are adjacent to each other may include two thermocouples. In this case, the vertex thermocouples 121 and 121 'measure the temperature of the reactor core 1002a as in a conventional core instrument set. In contrast, the lower thermocouple 125 included in the first core instrument set 10'a can be installed in the lower cavity 1001a of the nuclear reactor container under the reactor core 1002, and can measure the temperature of the lower cavity 1001a of the reactor. nuclear reactor container. The lower thermocouple 125 'included in the second core instrument set 10'b is installed in the bottom cover 100lb of the nuclear reactor container placed under the reactor core 1002, and can measure the temperature of the bottom cover 100lb of the nuclear reactor container. .
    [0009] Referring to Fig. 10, in accordance with another embodiment of the present invention, the system 1000 may include two core instrument sets 10'c and 10'd or more (five core instrument sets are illustrated on the Figure 10).
    [0010] In this case, the vertex thermocouples 121 and 121 'of the first and second core instrument assemblies 10'c and 10'd which are adjacent to each other measure the temperature of the reactor core 1002a as in a classical heart instrument ensemble 10.
    [0011] The lower thermocouple 125 or 125 'of the first and second core instrument sets 10'c or 10'd is alternately installed in the lower cavity 1001a of the nuclear reactor container or the lower cover 100lb of the nuclear reactor container placed under the reactor core 1002, and can measure the temperature of the lower cavity 1001a of the nuclear reactor container or the bottom cover 100lb of the nuclear reactor container. For example, the lower thermocouple 125 of the first core instrument set 10'c and the lower thermocouple 125 'of the second core instrument set 10'd may be installed at heights at which they are useful for the lower thermocouple 125 to measure the temperature. of the lower cavity 1001a of the nuclear reactor container and the lower thermocouple 125 'measures the temperature of the bottom cover 100lb of the nuclear reactor container. The thermocouples 122, 123 and 122 ', 123' which belong to the thermocouples of the core instrument sets 10'c and 10'd in accordance with another embodiment of the present invention and which are placed within the reactor core 1002 may be disposed adjacent to the dimples of the guide tubes 1005 which form physical contacts between the guide tubes 1005 and the core instrument sets 10'c and 10'd so that a surrounding temperature is rapidly measured. Each of the thermocouples may have the most equal space size within the reactor core 1002, and the shape of the space of each thermocouple may be almost a sphere for the thermocouples to measure temperatures at different heights within the reactor core 1002. 1002. For example, if first to fifth thermocouples 121, 122, 123, 124 and 125 are included in the first core instrument set 10'c and first to fifth thermocouples 121 ', 122', 123 ' , 124 'and 125' are included in the second core instrument set 10'd within a nuclear reactor (e.g., APR1400 in Korea) in which a reactor core is 162 inches in height at a time. the first thermocouples 121 and 121 'of the first core instrument set 10'c and the second core instrument set 10'd may be installed in the reactor core 1002a. The second thermocouple 122 of the first core instrument set 10'c can be installed at a dimple location on the upper side of the guide tube 1005, its third thermocouple 123 can be installed at a dimple location on the lower side of the 1005 guide tube, and its fourth thermocouple 124 can be installed at the bottom of reactor core 1002b. The second thermocouple 122 'of the second core instrument set 10'd may be disposed at a height between the first thermocouple 121 and the second thermocouple 122 of the first core instrument set 10'c, the third thermocouple 123' of the second instrument set 10'd heart can be arranged at a height between the second thermocouple 122 and the third thermocouple 123 of the first set of 10'c heart instrument, and the fourth thermocouple 124 'of the second 10'd heart instrument set can be installed in the 1002b reactor core bottom as the fourth thermocouple 124 of the first set 10'c heart instrument.
    [0012] As described above, in accordance with another embodiment of the present invention, the heights of the second thermocouples 122 and 122 'and the third thermocouples 123 and 123' of the first core instrument set 10'c and the second set of instruments 10'd heart that are adjacent to each other are arranged to cross each other. Accordingly, there is the advantage that the reliability of the temperature sensing within the reactor core 1002 depending on the height can be improved although separate thermocouples are not added.
    [0013] A type K thermocouple can be used as a thermocouple according to an embodiment of the present invention, and can detect 0 to 1260 at a measurement point. The K-type thermocouple is a thermocouple in which the ends of different types of metals (eg, chromel and alumel) are connected. A small electromotive force is generated at the other end of the type K thermocouple to which heat is applied at a temperature. The type K thermocouple can measure a temperature by sending the electromotive force. Therefore, if the heights of two or more K-type thermocouples are arranged differently in the length direction (i.e., the lengths of the thermocouples are different) as in one embodiment of the present invention, the Type K thermocouples can measure temperatures at different heights. The conventional core instrument assembly only measures the temperature of the reactor core top 1002a, but can not provide the temperatures of the remaining reactor core 1002 and the lower cavity 1001a or the lower lid 100lb of the nuclear reactor container. As a result, experts need to estimate the internal state of the nuclear reactor based on conditions outside the nuclear reactor. In this process, there are problems that different views for the estimate need to be adjusted, time is taken for the estimation task, and an error may appear in the estimation results.
    [0014] The core instrument assembly 10 'in accordance with one embodiment of the present invention can measure bottom temperatures of a reactor core at the top of the reactor core, can provide cooling, overheating, oxidation and the location status of a serious damage, and can determine the severity of an accident, the speed of deterioration and an accident location. As a result, a security threat can be minimized due to a serious accident due to a condition within a nuclear reactor, and a threat in terms of a security function in response to serious accident and we can take adequate measures in time. In particular, there are advantages in that 1) one can determine if the cooling of a reactor core is correct or not and 2) one can estimate a water level within a nuclear reactor based on on the temperature of each portion of the reactor core and on a change of temperatures, 3) it can be determined whether the cooling of the reactor core is appropriate or not inside the nuclear reactor based on the degree of oxidation and on serious damage to the reactor core, and 4) one can estimate the amount of hydrogen that can explode based on the degree of oxidation of the reactor core. In addition, it is possible to verify a serious accident and the state of a molten reactor core disposed under the reactor core based on a temperature distribution of the thermocouple 125 and the lower cavity 1001a and the lower cover 100lb under the nuclear reactor container. Accordingly, a threat and a moment for deviation of the molten reactor core from nuclear reactor container can be determined, and important information required to prepare a solution for a severe accident reduction strategy, such as securing the integrity of a nuclear reactor by external cooling of the nuclear reactor, can be provided. The diagnostic unit 1200 in accordance with one embodiment of the present invention can determine a serious damage to the reactor core 1002 based on the oxidation of the reactor core materials and the time during which the materials are exposed. at a high temperature. The amount of Zircaloy oxidation attributable to a hydration reaction in the representative space of a specific thermocouple and the amount of hydrogen generated in response to the amount of Zircaloy oxidation is calculated using a hydration reaction equation using the temperature of a corresponding thermocouple after an accident, the time during which Zircaloy is exposed to the corresponding temperature, and a vapor concentration derived from the water level of a reactor container nuclear. The degree of damage to the reactor core of a representative space can be estimated based on the degree of oxidation of all types of Zircaloy attributable to a hydration reaction and a change in the temperature of a core. reactor.
    [0015] In addition, a total amount of hydrogen generated in the nuclear reactor 1001 is determined by adding the hydrogen amounts generated in the representative spaces of the respective thermocouples 121, 122, 123, 124 and 125. In accordance with one embodiment of the present invention, 50 to 70 core instrument sets 10 'may be inserted into the nuclear reactor 1001. 61 core instrument assemblies 10' may be inserted into a nuclear reactor (e.g., APR1400 now operating in Korea). In accordance with one embodiment of the present invention, each of the thermocouples 121, 122, 123 and 124 of the reactor core 1002 has a specific gap formed according to the same distance rule with another adjacent thermocouple within the reactor core. 1002. This is defined as the representative spaces of a specific thermocouple, and the amount of fuel cladding that is included in a corresponding representative space and that generates a hydration reaction is also defined. A method of monitoring a nuclear reactor after a severe accident in accordance with an embodiment of the present invention may include steps of disposing two or more thermocouples in a core instrument set, arrangement of the two thermocouples or more to different heights in one direction of the length, insertion of the two or more core instrument sets into a nuclear reactor, and measurement of reactor core temperature via the thermocouples.
    [0016] The method of monitoring a nuclear reactor after a severe accident in accordance with an embodiment of the present invention may further include determining at least one of: damage or non-reactor damage, the location of a damaged reactor core, the state in which the molten reactor core has been rearranged, and the moment when a molten reactor core enters the nuclear reactor based on a temperature within the measured nuclear reactor in the step of measuring temperatures at different heights within the nuclear reactor via thermocouples. In this case, at least one of: the damage or not of the reactor core, the location of the damaged reactor core and the amount of hydrogen generated in the nuclear reactor, may be based on the oxidation of reactor core materials and the time during which the materials are exposed to a high temperature. This has been described above in detail. Alternatively, at least one of the state in which a molten reactor core has been rearranged and the moment the molten reactor core enters the nuclear reactor may be based on the temperature of the bottom or bottom lid under the nuclear reactor. This has been described above in detail. In accordance with the core multithermocouple instrument assembly according to one embodiment of the present invention, the internal state of a nuclear reactor can be more accurately diagnosed and the use of an apparatus can be maximized because Temperature at different heights within the nuclear reactor are provided using a plurality of thermocouples having temperature measurement points at different heights. The system and method for monitoring the internal state of a nuclear reactor after a severe accident in accordance with an embodiment of the present invention is advantageous because it serves as a support for the entry into a serious accident and an accident. crucial decision for a power plant can be determined quickly based on the severity of an accident and the rate of progress by monitoring a temperature in each portion of a reactor core and the water level of a reactor container nuclear. In addition, the system and method for monitoring the internal state of a nuclear reactor after a severe accident in accordance with an embodiment of the present invention is advantageous because they provide temperature information about the interior. of a nuclear reactor although a reactor core outlet temperature measurement instrument initially used in a severe accident is lost by monitoring a temperature in each portion of a reactor core. In addition, the system and method for monitoring the internal state of a nuclear reactor after a severe accident in accordance with an embodiment of the present invention is advantageous because it can determine a threat to a cooling function of the reactor. reactor core, namely, a safety functionality of a nuclear reactor, and provide information by which one can monitor whether an existing safety action is effective because one can check whether a corresponding portion is cooled or superheated and a speed cooling or overheating of the corresponding portion by monitoring a temperature in each portion of the reactor core. In addition, the system and method for monitoring the internal state of a nuclear reactor after a severe accident in accordance with an embodiment of the present invention is advantageous because it can provide information by which one can know if an operation for introducing a coolant into a nuclear reactor in order to cool a reactor core following a state of serious damage to each portion is effective for the reactor core when a serious accident is generated in a power plant nuclear. In addition, the system and method for monitoring the internal state of a nuclear reactor after a severe accident in accordance with an embodiment of the present invention is advantageous because they can provide information required for an operation. removal of hydrogen within a nuclear reactor containment building and required to prevent the explosion of hydrogen based on the amount of hydrogen generated by the oxidation of a reactor core when Serious accident is generated in a nuclear power plant. In addition, the system and method for monitoring the internal state of a nuclear reactor after a severe accident in accordance with an embodiment of the present invention is advantageous because it can optimally determine when the operation external cooling of a nuclear reactor is started based on the state in which the molten reactor core has been rearranged in the lower cavity of a nuclear reactor container according to the expiration of a severe accident and the a state in which a molten reactor core has deviated from the lower lid of the nuclear reactor container and may contain a molten reactor core within the barrier of the nuclear reactor container.
    权利要求:
    Claims (9)
    [0001]
    REVENDICATIONS1. A system for monitoring an internal state of a nuclear reactor (1001) after a severe accident, the system comprising: a core instrument assembly (10 ') inserted into the nuclear reactor (1001) and configured to measure neutrons and a temperature within the nuclear reactor (1001); and a diagnostic unit (1200) configured to determine a state of the nuclear reactor (1001) based on a temperature measured by the core instrument set (121 to 125), wherein the core instrument set (121 15 to 125) comprises two or more thermocouples (121 to 125), and two or more core instrument sets (121 to 125) are inserted and disposed in the nuclear reactor (1001) at a specific interval. 20
    [0002]
    The system of claim 1, wherein the two thermocouples (121 to 125) or more have different heights in a lengthwise direction. 25
    [0003]
    3. System according to claim 2, wherein the diagnostic unit (1200) determines at least one of: the damage or not of a reactor core (1002), a location of a reactor core damaged a quantity of hydrogen generated in the nuclear reactor (1002), a state in which a molten reactor core has been repositioned, and a moment when a molten reactor core enters the nuclear reactor (1001) based on a temperature measured by the two thermocouples (121 to 125) or more.
    [0004]
    4. System according to claim 3, wherein at least one of: the damage or not the reactor core (1002), the location of the damaged reactor core and the amount of hydrogen generated in the nuclear reactor ( 1001) is determined based on oxidation of the reactor core materials (1002) and a time during which the materials are exposed to a high temperature.
    [0005]
    The system of claim 3, wherein at least one of the state in which the molten reactor core has been rearranged and the moment the molten reactor core enters the nuclear reactor (1001) is determined by based on a lower cavity temperature below the nuclear reactor (1001) or a lower cover (1001b).
    [0006]
    6. A method of monitoring an internal state of a nuclear reactor (1001) after a severe accident using a core instrument assembly (10 '), the method comprising the steps of: (A) disposing of two thermocouples (121) 125) or more in the core instrument set (10 '); (B) providing two or more thermocouples (121 to 125) at different heights in a length direction; (C) inserting two or more core instrument sets into the nuclear reactor (1001); and (D) measuring temperatures at different heights within the nuclear reactor (1001) through the thermocouples (121 to 125).
    [0007]
    The method of claim 6, further comprising a step of (E) determining at least one of: damage to a reactor core (1002), a location of a core of reactor, a quantity of hydrogen generated in the nuclear reactor (1001), a state in which a molten reactor core has been rearranged, and a moment when a molten reactor core enters the nuclear reactor (1001) 15 based on on a temperature within the nuclear reactor (1001) measured in step (D).
    [0008]
    The method of claim 7, wherein at least one of: damage to the reactor core (1001), the location of the damaged reactor core, and the amount of hydrogen generated in the nuclear reactor is determined based on oxidation of reactor core materials (1002) and a time during which the materials are exposed to a high temperature.
    [0009]
    The process according to claim 7, wherein at least one of the state in which the molten reactor core has been redisposed and the moment the molten reactor core enters the nuclear reactor (1001) is determined by based on a lower cavity temperature beneath the nuclear reactor (1001) or a lower cover.
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    同族专利:
    公开号 | 公开日
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    US20160055926A1|2016-02-25|
    FR3029344B1|2021-07-02|
    JP2016045191A|2016-04-04|
    CN105387948A|2016-03-09|
    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    US4288291A|1979-05-11|1981-09-08|Whittaker Corporation|Radiation detector for use in nuclear reactors|
    US4426352A|1980-11-14|1984-01-17|The Babcock & Wilcox Company|Composite detector|
    JPS57203996A|1981-06-10|1982-12-14|Tokyo Shibaura Electric Co|Device for monitoring inside of reactor|
    JPS63108297A|1986-10-27|1988-05-13|Nippon Atomic Ind Group Co|Fuel soundness monitor in nuclear reactor core|
    US4780267A|1987-02-17|1988-10-25|Westinghouse Electric Corp.|In-core assembly configuration having a dual-wall pressure boundary for nuclear reactor|
    US5251242A|1992-06-22|1993-10-05|Westinghouse Electric Corp.|Bi-metallic, self powered, fixed incore detector, and method of calibrating same|
    FR2753299B1|1996-09-12|1999-03-05|Commissariat Energie Atomique|MINIATURIZED, SELF-POWERED, FAST RESPONSE DEVICE FOR THE STAGE DETECTION OF A NEUTRONIC FLOW, PARTICULARLY IN A NUCLEAR REACTOR|
    KR101034386B1|2010-09-28|2011-05-16|주식회사 창성에이스산업|Temperature measuring cable|
    US8681920B2|2011-01-07|2014-03-25|Westinghouse Electric Company Llc|Self-powered wireless in-core detector|
    JP5740288B2|2011-11-22|2015-06-24|株式会社東芝|Reactor water level measurement system|
    JP5980500B2|2011-12-13|2016-08-31|株式会社日立製作所|Reactor water level gauge|
    KR101484000B1|2012-05-04|2015-01-19|한국수력원자력 주식회사|Hybrid Incore Detector Assembly for Core Monitoring And Protection using eXtended Length|
    US20140376678A1|2013-06-25|2014-12-25|Robert H. Leyse|Method of and Apparatus for Monitoring a Nuclear Reactor Core Under Normal and Accident Conditions|CN106024078B|2016-06-24|2017-08-25|西安交通大学|A kind of method of diagnostic reaction pile neutron detector failure|
    CN106448839B|2016-10-12|2017-10-27|浙江伦特机电有限公司|Instrument cable for nuclear power station component|
    CN106531245B|2016-11-25|2018-11-13|浙江伦特机电有限公司|Used in nuclear power station in-pile instrument sheath assembly|
    CN108376571B|2018-01-24|2019-10-22|中广核研究院有限公司|Core temperature measuring device for reactor|
    CN108760063B|2018-05-22|2021-01-01|安徽瑞鑫自动化仪表有限公司|Intelligent regulation and control method for high-temperature detection|
    CN110111917B|2019-04-17|2020-11-06|中广核工程有限公司|Method and device for monitoring neutron flux of out-of-reactor nuclear reactor after accident and readable storage medium|
    CN111477366B|2020-02-28|2021-11-23|中广核研究院有限公司|Detector assembly integrating reactor core measuring function|
    CN113029388A|2021-02-24|2021-06-25|中国核动力研究设计院|Positioning device capable of improving positioning precision of reactor core detector assembly sensor|
    法律状态:
    2016-08-11| PLFP| Fee payment|Year of fee payment: 2 |
    2017-08-31| PLFP| Fee payment|Year of fee payment: 3 |
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    2020-06-05| PLSC| Search report ready|Effective date: 20200605 |
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    2021-08-31| PLFP| Fee payment|Year of fee payment: 7 |
    优先权:
    申请号 | 申请日 | 专利标题
    KR1020140111111A|KR101621236B1|2014-08-25|2014-08-25|Incore instrument assembly with multi type thermo-coupler|
    KR1020140111106A|KR101671312B1|2014-08-25|2014-08-25|Multipoints thermocouple in In-Core Instrument assembly, system and method for post severe accident reactor internal status monitoring using the same|
    FR1557824A|FR3025048B1|2014-08-25|2015-08-20|MULTITHERMOCOUPLE HEART INSTRUMENT ASSEMBLY AND SYSTEM AND METHOD FOR MONITORING THE INTERNAL STATE OF A NUCLEAR REACTOR AFTER A SERIOUS ACCIDENT USING IT|
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